Text

Reactor Vessel Neutron Fluence Measurement Program for Cpc,Results to End of Cycle 9.
	ML18058B874
Person / Time
Site:	Palisades
Issue date:	05/31/1993
From:	Fero A, Lau F, Lippincott E; WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	;
Shared Package
ML18058B873	List: ML18058B872; ML18058B874;
References
	WCAP-13534, WCAP-13534-R02, WCAP-13534-R2, NUDOCS 9306150379
	Download: ML18058B874 (236)
	v • d • e

Westinghouse Class 3 (Non-proprietary)

WCAP-13534 Revision 2(.,~1993)

Palisades Nuclear Plant Reactor Vessel Neutron Fluence Measurement Program for Consumers Power Company Results to End of Cycle 9 E. P. Lippincott

/

A.H. Fero T. M. Lloyd March 1993 APPROVED: -~-----'-~--~~'_.;..J{/a......,.av--=---

F. L. Lau, Manager Radiation Engineering and Analysis Prepared by Westinghouse for the 0Consumers Power Company Purchase Order No. C0000920 and C0000921 Work performed under Shop Order No. MGAP-450 and MGBP-450

,,_- 93061 so379-9:1o6i

~DP. ADOCX o5ooo255 WESTINGHOUSE ELECTRIC CORPORATION o- - --.-. .

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Energy Systems Business Unit P.O. Box 355 .

Pittsburgh, Pennsylvania 15230 PDR ,

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ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 PRESSURIZED THERMAL SHOCK REACTOR VESSEL NEUTRON FLUENCE WESTINGHOUSE REPORT, WCAP-13534 (REV. 2)

May 1993 PALISADES NUCLEAR PLANT REACTOR VESSEL NEUTRON FLUENCE MEASUREMENT PROGRAM FOR CONSUMERS POWER COMPANY RESULTS TO THE END OF CYCLE 9 J.une 1993

Table of Contents Section Title Overview of the Program .......... *....................... .

l-l 2 Description of the Measurement Program . . . . . . . . . . . . . . . . . . . . . . . 2-1 2-1. Description of Reactor Cavity Neutron Dosimetry . . . . . . . . . . . . . 2-1 2-2. Sensor Placement in the Reactor Cavity . . . . . . . . . . . . . . . . . . . . 2-2 2-3. Description of Reactor Cavity Irradiation Capsules . . . . . . . . . . . . . 2~2 2-4. Description qf Reactor Cavity Gradient Chains . . . . . . . . . . . . . . . . 2-3 2-5. Description of In-Vessel Dosimetry Capsule .......... ~ . . . . . . . 2-3 3 Neutron Transport and Dosimetry Evaluation Methodologies . . . . . . . . . 3-1 3-1. Neutron Transport Analysis Methods . . . . . . . . . . . . . . . . . . . . . . . 3-1 3-2. Neutron Dosimetry Evaluation Methodology . . . . . . . . . . . . . . . . . . 3-4 3-3. Least Squares Adjustment Procedure . . . . . . . . . . . . . . . . . . . . . . . 3-6 4 Results of Neutron Transport Calculations . . . . . . . . . . . . . . . . . . . . . . . 4-1

4-1. Reactor Cavity Sensor Set Locations . . . . . . . . . . . . . . . . . . . . . . . 4-1 4-2. In-Vessel Dosimetry Capsule . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 4-3. Reactor Vessel Wall . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-2 5* Evaluation of Cycle 9 In-Vessel Dosimetry Capsule . . . . . . . . . . . . . . . . 5-1 5-1. Measured Reaction Rates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1

5-2. Results of the Least Squares Adjustment Procedure ............. 5-2 6 Evaluations of Reactor Cavity Dosimetry . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 6-1. Cycle 8 Measured Reaction Rates . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 6-2. Cycle 9 Measured Reaction Rates .......... '. * . . . . . . . . . . . . . . 6-4 6-3. *Results of the Least Squares Adjustment.Procedure . : ........... 6-8' 7 Comparison of Calculations with Measurements . . . . . . . . . . . . . . . . . . . 7-1

7-1. Comparison of Least Squares Adjustment Results with Calculation .. 7-2 7-2 .. Comparison of Measured and Calculated Sensor Reaction Rates .... 7-3.

lll

- Table of Contents (continued)

Section Title 8 Best Estimate Neutron Exposure of Reactor Vessel Materials 8-1 9 Summary and Conclusions ................................... 9-1 10 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . *._ . . . 10- 1 Appendix A - Irradiation History and Measured Specific Activities A-1 Appendix B - Calculated and Adjusted Flux Spectra .. .'. . . . . . . . . . . . B-1 lV

Table Title List of Table-s Page 2-1 Measured Neutron Reactions *. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-5 2-2 Azimuthal Locations for Palisades Cycle 8 Reactor Cavity Measurements 2-6 i 2-3 Azimuthal Locations for Palisades Cycle 9 Reactor Cavity Measurements 2-7

4-1 Calculated Neutron Energy Spectra at Cavity Sensor Set Locations for Cycle 8 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .- ....... 4-3 4-2 Calculated Neutron Energy Spectra at Cavity Sensor Set Locations for Cycle 9 . . . . . . . . . . . . . . . . . . . . . . . . . . . . ~ . . . . . . . . . . . . . . . . 4-5 4-3 Calculated Neutron Energy Spectra at the 290° Capsule Center for Cycle 9 . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . 4-7 4-4 Azimuthal Variation of Fast Neutron Flux (E > 1.0 MeV) at the Reactor Vessel Clad-Base Metal Interface . . . . . . . . . . . . . . . . . . . . . . . 4-8 4-5 Summary of Fast Neutron Exposure Rates at the Reactor Vessel Clad-Base Metal Interface . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-11 4-6 Relative Radial Distribution of Neutron Flux (E > 1.0 Me V) within the Reactor Vessel Wall for Cycle 8 . . . . . . . . . . . . . . . . . . . . . . . . . . 4-12 4-7 Relative Radial Distribution of Neutron Flux (E > 1.0 Me V) within the Reactor Vessel Wall for Cycle 9 . . . . . . . . . . . . . . . . . . . . . . . . . . 4-13 4-8 Relative Radial Distribution of Neutron Flux (E > 1.0 Me V) within the Reactor Vessel Wall Average for Cycles 8 and 9 . . . . . . . . . . . . . . . 4-14 4-9 Relative Radial Distribution of Neutron Flux (E > 0.1 Me V) within the Reactor Vessel Wall for Cycle 8 . . . . . . . . . . . . . . . . . . . . . . . . . . 4--15 4-10 Relative Radial Distribution of Neutron Flux (E > 0.1 Me V) within the Reactor Vessel Wall for Cycle 9 . . . . . . . . . . . . . . . . . . . . . . . . . . 4-16 4-11 Relative Radial Distribution of Neutron Flux (E > 0.1 Me V) within

. the Reactor Vessel Wall Average for Cycles 8 and 9 . . . . . . . . . . . . . . . 4- 17 4-12 Relative Radial Distribution of Iron Atom Displacement Rate (dpa/s) within the Reactor Vessel Wall for Cycle 8 . . . . . . . . . . . . . . . . . . . . . 4-18 4-13 Relative Radial Distribution of Iron Atom Displacement Rate (dpa/s) within the Reactor Vessel Wall for Cycle 9 . . . . . . . . . . . . . . . . . . . . . 4-19 4-14 Relative Radial Distribution of Iron Atom Displacement Rate (dpa/s) within the Reactor Vessel Wall Average for Cycles 8 and 9 .......... 4-20 v

Table Title List of Tables (continued) 5-1 Summary of Reaction Rates Derived from Multiple Foil Sensor Sets in the W-290 In-Vessel Dosimetry Capsule Irradiated During Cycle 9 5-4 5-2 Palisades_ Cycle 9 In-Vessel Dosimetry Top Capsule (lAlF) Results ..... 5-5 5-3 Palisades Cycle 9 In-Vessel Dosimetry Middle Capsule (1A4F) Results ... 5-6 5-4 Palisades Cycle 9 In- Vessel Dosimetry Bottom Capsule { 1A7F) Results . . . 5-7 5-5 Palisades Cycle 9 In-Vessel Dosimetry Capsule (20 Degree Midplane)

Average Results ......................................... 5-8 5-6 Palisades Cycle 1-5 W-290 Surveillance Capsule (20 Degree Midplane)

Average Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-9 6-1 Location of Cycle 8 Support Bar Mounted Dosimetry in the Reactor Cavity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-10

6-2 6-3 Summary of Reaction Rates derived from Multiple Foil Sensor Sets Irradiated During *Cycle 8 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 1 Reaction Rates Derived from the Support Bar Mounted Stainless Steel

- Gradient Chains Irradiated During Cycle 8 . . . . . . . . . . . . . . . . . . . . . . 6::.12 6-4 Reaction Rates Derived from the Long Stainless Steel Gradient Chains Irradiated During Cycle 8 . . *. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-16 6-5 Average Reaction Rates Derived from the Three Symmetric 30 Degree Stainless Steel Gradient Chains Irradiated During Cycle 8 ........... 6-22 6-6 Location of Cycle 9 Support Bar Mounted Dosimetry in the Reactor Cavity . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-23 6-7 Summary of Reaction Rates derived from Multiple Foil. Sensor Sets Irradiated During Cycle 9 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-24 6-8 _. Reaction Rates Derived from the Support Bar Mounted Stainless Steel Gradient Chains Irradiated During Cycles 8 and 9 ................. 6-25 6-9 Reaction Rates Derived from the Support Bar Mounted- Stainless Steel Gradient Chains Irradiated During Cycle 9 ...................... 6-26 6-10 Reaction Rates Derived from the Long Stainless Steel Gradient Chains

6-11 6-12

. 6-13 Irradiated During Cycle 9 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Palisades Cycle 8 Cavity Dosimetry 16° Midplane Results ...........

Palisades Cycle 8 Cavity Dosimetry 26° Midplane Results ...........

Palisades Cycle 8 Cavity Dosimetry 26° Core Bottom Results . . . . . . . .

6-30 6-35 6-36 6-37 Vl

Table Title List of Tables (continued) 6-14 Palisades Cycle 8 Cavity Dosimetry 39° Midplane Results ........... 6-38 6-15 Palisades Cycles 8-9 Cavity Dosimetry 6° Midplane Results .......... 6-39 6-16 Palisades Cycles 8-9 Cavity Dosimetry 6° Core Bottom Results ....... 6-40 6-17 Palisades Cycle 9 Cavity Dosimetry 16° Midplane Results . . . . . . . . . . . 6-41 6-18 Palisades Cycle 9 Cavity Dosimetry 26° Midplane Results . . . . . . . . . . . 6-42 6-19 Palisades-Cycle 9 Cavity Dosimetry 26° Core Bottom Results . . . . . . . . 6-43 6-20 Palisades Cycle 9 Cavity Dosimetry 39° Midplane Results . . . . . . . . . . . 6-44 6-21 Palisades Cavity Axial Flux Profile . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-45 7-1 Comparison of Measured and Calculated Exposure Rates from Palisades Dosimetry Irradiations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7-4 7-2 Comparison of FERRET and Reaction Rate Average C/M Ratios . . . . . . . 7-7

8-1 8-2 Summary of Best Estimate Fast Neutron (E > 1.0 MeV) Exposure for the Inner Radius of the Palisades Reactor Vessel for Cycles 8 and 9 ..... 8-4 Summary of Best Estimate Fast Neutron (E > 0.1 Me V) Exposure for the Inner Radius of the Palisades Reactor Vessel for Cycles 8 and 9 ..... 8-5 8-3 Summary of Best Estimate Iron Atom Displacements for the Inner Radius of the Palisades Reactor Vessel for Cycles 8 and 9 . . . . . . . . . . . . . . . . . 8-6 8-4 Palisades Fast Neutron Fluence (E > 1.0 Me V) Through Cycle 9 at the Reactor Vessel Clad-Base Metal Interface . . . . . . . . . . . . . . . . . . . . . . . 8-7 A-1 Palisades Cycle 8 Thermal Power Generation . . . . . . . . . . . . . . . . . . . . A-2 A-2 Palisades Cycle 9 Thermal Power Generation . . . . . . . . . . . . . . . . . . . . A-3 A-3 Dosimeter Capsule Contents Installed for Cycle 8 . . . . . . . . . . . . . . . . . A-4 A-4 Dosimeter Capsule Contents Installed for Cycle 9 . . . . . . . . . . . . . . . . . A-5 A-5 Palisades Cycle 8 Reactor Cavity Dosimetry Set Results . . . . . . . . . . . . A-6 A-6 Palisades Cycle 8 Reactor Cavity Gradient Chain Measurements ....... A-10 A-7 Palisades Cycle 9 Reactor Cavity Dosimetry Set Results ............ A-20 A-8 Palisades Cycle 9 Reactor Cavity Gradient Chain Measurements ....... A-27 A-9 Palisades Cycle 9 In-Vessel Dosimetry Capsule Results ............. A-38 vii

Table Title List of Tables (continued)

B-1 FERRET Spectrum Result - Palisades In-Vessel Capsule at 20° Midplane Cycle 9 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-2 B-2 FERRET Spectrum Result - Palisades W-290 Capsule at 20° Midplane Cycles 1-5 ....................* ....................... *. B-4 B-3 FERRET Spectrum Result - Palisades Cavity at 16° Midplane Cycle 8 . . B-6 B-4 FERRET Spectrum Result - Palisades Cavity at 26° Midplane Cycle 8 . . B-8 B-5 FERRET Spectrum Result - Palisades Cavity at 26° Bottom Cycle 8 .... B-10 B-6 FERRET Spectrum Result - Palisades Cavity at 39° Midplane Cycle 8 .. B-12 B-7 FERRET Spectrum Result - Palisades Cavity at 0° Midplane Cycle 8-9 .. B-14 B-8 FERRET Spectrum Result - Palisades Cavity at 0° Bottom Cycle 8-9 ... B-16 B-9 FERRET Spectrum Result - Palisades Cavity at 16° Midplane Cycle 9 .. B-18 B-10 FERRET Spectrum Result- Palisades Cavity at 26° Midplane Cycle 9 .. B-20 B-11 FERRET Spectrum Result - Palisades Cavity at 26° Bottom Cycle 9 .... B-22 B-12 FERRET Spectrum Result - Palisades Cavity at 39° Midplane Cycle 9 .. B-24 Vlll

List of Figures Figure Title 2-1 Reactor Cavity Neutron Dosimetry Reference Coordinate System . . . . . . 2-8 2-2 In-Vessel Dosimetry Capsule Assembly . . . . . . . . . . . . . . . . . . . . . . . . . 2-9 2-3 In-Vessel Dosimetry Capsule Compartment Assemblies ............. 2-10 3-1 Reactor Geometry Showing a 45° R,0 Sector for the Inner Part of the Model for Cycle 8 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-10 3-2 Reactor Geometry Showing a 45° R,0 Sector for the Inner Part of the Model for Cycle 9 . . . . . . . . . . . . . . . . . . -. . . . . . . . . . . . . . . . . . . . . 3-11 3-3 Reactor Geometry Showing a 45° R,0 Sector for the Outer Part of the Model for Cycles 8 and 9 . . . : . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-12 6-1 Palisades Cycle 8 Fe-54 (n,p) Mn-54 Reaction Rate vs Angle ......... 6-46

6-2 6-3 6-4 6-5 Palisades Cycle 8 Ni-58 (n,p) Co-58 Reaction Rate vs Angle ......... 6-47 Palisades Cycle 8 Fe-54 (n,p) Mn-54 Reaction Rate vs Angle ......... 6-48 Palisades Cycle 8 Ni-58 (n,p) Co-58 Reaction Rate vs Angle ......... 6-49 Palisades Cycle 8 Short Chains Fe-54 (n,p) Mn-54 Reaction Rate vs Z .. 50 6-6 Palisades Cycle 8 Short Chains Ni-58 (n,p) Co-58 Reaction Rate vs Z ... 6-51 6-7 Palisades Cycle 8 Short Chains Co-59 (n,y) Co-60 Reaction Rate vs Z .. 6-52 6-8 Palisades Cycle 8 Long Chains Fe-54 (n,p) Mn-54 Reaction Rate vs Z .. 6-53 6-9 Palisades Cycle 8 Long Chains Ni-58 (n,p) Co-58 Reaction Rate vs Z ... 6-54 6~ l 0 Palisades Cycle 8 Long Chains Co-59 (n,y) Co-60 Reaction Rate vs Z . . 6-55 6-11 Palisades Cycle 8 0° Chain Fe-54 (n,p) Mn-54 Reaction Rate vs Z ..... 6-56 6-12 Palisades Cycle 8 Z0° Chain Fe-54 (n,p) Mn-54 Reaction Rate vs Z .... 6-57 6-13 Palisades Cycle 8 30° Avg Chain Fe-54 (n,p) Mn-54 Reaction Rate vs Z . 6-58 6-14 Palisades Cycle 8 0° Chain Ni-58 (n,p) Co-58 Reaction Rate vs Z ..... 6-59 6-15 Palisades Cycle 8 Z0° Chain Ni-58 (n,p) Co-58 Reaction Rate vs Z . . . . . 6-60 6-16 Palisades Cycle 8 30° Avg Chain Ni-58 (n,p) Co-58 Reaction Rate vs Z . 6-61 6-17 Palisades Cycle 9 Fe-54 (n,p) Mn-54 Reaction Rate vs Angle . . . . . . . . . 6-62 6-18 Palisades Cycle 9 Ni-58 (n,p) Co-58 Reaction Rate vs Angle ......... 6-63

6-19 6-20 Palisades Cycle 9 Fe-54 (n,p) Mn-54 Reaction Rate vs Angle ......... 6-64 Palisades Cycle 9 Ni-58 (n,p) Co-58 Reaction Rate vs Angle ......... 6-65 ix

Figure Title List of Figures (continued) 6-21 Palisades Cycle 9 Short Chains Fe-54 (n,p) Mn-54 Reaction Rate vs Z 6-66 6-22 Palisades Cycle 9 Short Chains Ni-58 (n,p)

Co-58 Reaction Rate vs Z ... 6-67 6-23 . Palisades Cycle 9 Short Chains Co-59 (n,y) Co-60 Reaction Rate vs Z . . 6-68 6-24 Palisades Cycle 9 Long Chains Fe-54 (n,p) Mn-54 Reaction Rate vs Z .. 6-69 6-25 Palisades Cycle 9 Long Chains Ni-58 (n,p) Co-58 Reaction Rate vs Z ... 6-70 6-26 Palisades Cycle 9 Long Chains Co-59 (n,y) Co-60 Reaction Rate vs Z . . 6-71 6-27 Palisades Cycle 9 0° Chain Fe-54 (n,p) Mn-54 Reaction Rate vs Z ..... 6-72 6-28 Palisades Cycle 9 10° Chain Fe..:54 (n,p) Mn-54 Reaction Rate vs Z .... 6-73 6-29 Palisades Cycle 9 20° Chain Fe-54 (n,p) Mn-54 Reaction Rate vs Z .... 6-74 6-30 Palisades Cycle 9 30° Avg Chain Fe-54 (n,p) Mn-54 Reaction Rate vs Z . 6-75 6-31 Palisades Cycle 9 0° Chain Ni-58 (n,p) Co-58 Reaction Rate vs Z . . . . . 6-76 6-32 Palisades Cycle 9 10° Chain Ni-58 (n,p) Co-58 Reaction Rate vs Z ..... 6-77 6-33 Palisades Cycle 9 20° Chain Ni-58 (n,p) Co-58 Reaction Rate vs Z . . . . . 6-78 6-34 Palisades Cycle 9 30° Avg Chain Ni-58 (n,p) Co-58 Reaction Rate vs Z . 6-79 6-35 Palisades Axial Flux Profile . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-80 A-1 Photograph of Cycle 9 In-Vessel Capsule lAlF Dosimeters . . . . . . . . . . A-40 A-2 Photograph of Cycle 9 In-Vessel Capsule 1A4F Dosimeters . . . . . . . . . . A-41 A-3 Photograph of Cycle 9 In-Vessel Capsule 1A7F Dosimeters .......... A-42 x

Executive Summary Beginning with* Fuel Cycle 8, Consumers Power Company began a reacwr vessel fluence measurement program at the Palisades Plant to provide a data base for evaluation of the reactor vessel fast neutron exposure and to reduce the uncertainty in the exposure. This report presents the results of the successful reactor cavity neutron dosimetry measurements carried out during Fuel Cycles 8 and 9 and the in-vessel dosimetry capsule measurement performed during Cycle 9.

Together with the previous W-290 surveillance capsule measurement, these measurements establish a basis for validation of calculated reactor vessel fast neutron exposures at the key weld

. points.

Both Cycles 8 and 9 in Palisades were unique cycles designed to signifi~antly lower the reactor vessel exposure at key points. The reactor cavity dosimetry measurements for these cycles show good consistency and this indicates that the calculated flux reductions are predicted accurately.

In addition, the Cycle 9 in-vessel dosimetry measurement is consistent with the previous Cycle 1-5 W-290 surveillance capsule measurement. This consistency provides confidence that the calculations are able to track changes in reactor vessel exposure due to the changing core loading patterns, and, coupled with the measurements can provide accurate values for the vessel exposure. In addition, the simultaneous irradiation in Cycle 9 of the in-vessel and ex-vessel dosimetry provides a unique validation of the neutron transport calculation through the vessel wall.

For the Palisades Plant, the most limiting reactor vessel fast neutron exposure is to the circumferential beltline weld which has the peak fluence at angles symmetric with 16 degrees.

The exposure to the longitudinal welds at 0 degrees and 30 degrees is also important. Based on the comparisons of measurement results with calculations, it is concluded that the DOT calculations are conservative and overpredict the reactor vessel fast neutron fluence (E > 1.0 MeV) by six percent. Taking into account this six percent bias, the best estimate maximum ffuence at the end of Cycle 9 is l.52xl0 19 n/cm2 for the ciicumferential weld, l.1 lxl0 19 n/cm 2 for the longitudinal weld at 0 degrees, and l.12xl0 19 n/cm2 for the longitudinal weld at 30 degrees. The uncertainty in these values was estimated to be +/- 10 percent.

Continuation of the reactor vessel monitoring program will provide further data to improve the characterization of the neutron environment in the vessel and to record the effects of changing fuel cycles. This will enable the uncertainty in projection of the reactor vessel exposure to be reduced by basing the projections on realistic exposure levels with known uncertainties.

XI

Section 1 Overview of the Program In order to improve the accuracy of the assessment of the Palisades reactor vessel exposure, the Consumers Power Company has initiated a measurement program to supplement-*,theiimiied dosimetry information available from the two previously analyzed surveillance capsules. This measurement program consists of a replacement in-vessel dosimetry capsule that was irradiated in Fuel Cycle 9 and an ongoing reactor cavity measurement program that was started with Fuel Cycle 8. This report presents results *of the analysis of the in-vessel capsule and the *cycles 8 and 9 ex-vessel dosimetry. These cycles are particularly significant because they both represent configurations designed to lower the fluence rate to vessel welds which are of particular concern as limiting the vessel lifetime due to irradiation embrittlement. In addition, the neutron leakage is minimized to lower the fluence rate to the vessel peak fluence location. Since future cycles are also expected to be designed to minimize the fluence to the vessel plates and welds, measurement of the fluence at numerous points on the vessel can be expected to give increased accuracy for future projections of vessel exposure.

The Reactor Cavity Neutron Measurement Program [1,2] is designed to provide a mechanism for the long term continuous monitoring of the neutron exposure of those portions of the reactor vessel and vessel support structure which may experience radiation induced increases in reference nil ductility transition temperature (RTNDT) over the nuclear power plant lifetime. When used in conjunction with dosimetry from previously withdrawn internal surveillance capsules and with the results of neutron transport calculations, the reactor cavity neutron dosimetry provides the determination of the neutron exposure of the reactor vessel and the projection of embrittlement gradients through the vessel wall with a minimum uncertainty. Minimizing the uncertainty in the neutron exposure projections will, in turn, help to assure that the reactor can be operated in the least restrictive mode possible with respect to:

1- Appendix G pressure/temperature limit curves (10 CFR Part 50) for normal heat up and cool down of the reactor coolant system; 2- Emergency Response Guideline (ERG) pressure/temperature limit curves; and 3- *The Pressurized Thermal Shock (PTS) Rule (10 CFR 50.61) screening criteria.

1-1

In addition, an accurate measure of the neutron exposure of the reactor vessel and support structure can provide a sound basis for requalification should operation of the plant beyond the current design and/or licensed lifetime prove to be desirable.

Within the nuclear industry it has been common practice to base estimates of the fast neutron exposure of reactor vessels either directly on the results of neutron transport calculations or on the analytical results normalized to measurements obtained from internal surveillance capsules.

However, there are potential drawbacks associated with both of these approaches to exposure assessment.

In performing neutron transport calculations for pressurized water reactors, several design and operational variables have an impact on the magnitude of the analytical prediction of exposure rates within the reactor vessel wall as well as on the uncertainties associated with that prediction.

Examples of these variables are cycle-to-cycle variations in core power and fuel burnup distributions (especially with implementation of low leakage loading patterns), variations of water temperature in the downcomer regions of the reactor internals, and differences in as-built versus*

design dimensions for the reactor internals and reactor vessel. Treatment of these important variables in the analysis by plant-specific calculation of each cycle with benchmarking using in-vessel and ex-vessel neutron flux measurements may lead to a decreased uncertainty in the exposure evaluations for the reactor vessel; and, these decreased uncertainties may well provide the benefit of allowing a less conservative estimate of vessel embrittlement for the assessment of pressure temperature limitations as well as of the expected service life of the component.

Uncertainties in reactor vessel fluence evaluation also arise from the approximations and data errors that are an integral part of any transport calculation. The reactor model used has a finite number of points that have to represent geometry in a symmetry not always appropriate. In the case of typical two dimensional calculations of LWR geometries, the fuel and shroud region is in an x-y configuration while the other reactor components in the calculation (barrel, water gap, reactor vessel, etc.) are cylindrically symmetric. Errors due to such modeling difficulties can be minimized by use of a sufficient number of points to define the geometry and by paying close attention to preserving the volume of each component in the model. Other uncertainties may be introduced by the inclusion or exclusion of other .structures such as former plates and surveillance capsules that are not present symmetrically. Of importance also are cross section uncertainties

that can have large impacts on transport of neutrons through the region from the fuel to the reactor cavity. The existence of these uncertainties, together with the reactor geometry uncertainties mentioned above, require that the calculations be benchmarked to measured results, both related controlled benchmarks (such as the those measured under the NRC-sponsored LWR 1-2

Pressure Vessel Surveillance Dosimetry Improvement Program (LWR-PV-SDIP) [3]), and plant specific measurements at Palisades. The Westinghouse methodology has been benchmarked against a number of benchmarks including the PCA at ORNL [4], the VENUS mockup at Mo!,

Belgium [5], and the H. B. Robinson PWR [6], as well as against a large database of reactor surveillance capsule measurements and reactor cavity dosimetry measurements [7 ,81.

The Palisades reactor currently has a reactor vessel surveillance program which originally consisted of two accelerated surveillance capsules attached to the core barrel and six capsules attached to the reactor vessel wall. This program has been in service since the initial start up of the reactor. The neutron dosimetry contained in these capsules provides measurement capability to determine the fast neutron exposure of the materials test specimens .also located within the capsules. At the s~me time this measured exposure data can be used to validate the calculated reactor vessel exposure, but only at a single symmetric azimuthal location within the reactor geometry near the reactor vessel. Therefore, the surveillance capsule dosimetry, by itself, cannot provide information regarding the azimuthal and radial gradients of neutron exposure within the reactor vessel, and only limited axial information. Furthermore, data from internal surveillance*

capsules are, by design, obtained at rather infrequent intervals; and surveillance measurement locations may not be in proximity to critical areas on the reactor vessel. These limitations place a heavy reliance on analytical results to project exposure levels to the reactor vessel wall as well as to provide predictions of vessel exposure for time periods beyond the last scheduled capsule withdrawal.

With the addition of passive neutron sensors in the reactor cavity annulus between the reactor vessel wall and the biological shield, the deficiencies in both surveillance dosimetry and analytical prediction can be mitigated and the uncertainties associated with exposure estimates .

for the reactor vessel can be minimized. With neutron sensors deployed to establish the absolute magnitude of the azimuthal and axial exposure rate distributions in the reactor cavity, the burden placed on the neutron transport calculation is reduced to the determination of relative neutron energy spectra for sensor set interpretation and relative spatial distributions for extrapolation of the measurement results to positions at the inner radius and through the thickness of the reactor vessel wall. Studies have shown that even though the operational and design variables cited above have a strong impact on the calculated magnitude of exposure rates, they have only a minor effect on both the interpretation of reactor cavity dosimetry measurement results and on the extrapolation of exposure values to key reactor vessel locations. It is possible, therefore, to employ reactor cavity measurements and a set of reference neutron transport calculations to produce reactor vessel exposure projections with a reduced uncertainty over that inherent in an approach based on analysis alone. Furthermore, since the reactor cavity neutron measurements 1-3

are not directly tied to the materials surveillance program, measurement intervals can be chosen to easily provide integral reactor vessel exposure over plant lifetime.

The use of fast neutron fluence (E > 1.0 MeV) to correlate measured materials properties changes to the neutron exposure of the material for light water reactor applications has traditionally been accepted for development of damage trend curves as well as for the implementation of trend curve data to assess reactor vessel condition. In recent years. however, it has been suggested that an exposure model that accounts for differences in neutron energy spectra between surveillance capsule locations and positions within the vessel wall could lead to an improvement in the uncertainties associated with damage trend curves as well as to a more accurate evaluation of damage gradients through the reactor vessel wall. Because of this potential shift away from threshold fluence toward an energy dependent damage function for data correlation, ASTM Standard Practice E853, "Analysis and Interpretation of Light Water Reactor Surveillance Results" [9], recommends reporting displacements per iron atom (dpa) along with fluence (E > 1.0 Me V) to provide a data base for future reference. The energy dependent dpa function to be used for this evaluation is specified in ASTM Standard Practice E693, "Characterizing*

Neutron Exposures in Ferri tic Steels in Terms of Displacements per Atom" [ 10]. The application of the dpa parameter to the assessment of embrittlement gradients has already been promulgated in Revision 2 to Regulatory Guide 1.99, "Radiation Damage to Reactor Vessel Materials".

With the aforementioned views in mind, the Reactor Cavity Measurement Program was established to meet the following objectives:

1- Determine azimuthal and axial gradients of fast neutron exposure over the beltline region of the reactor vessel; 2- Provide measurement capability sufficient to allow the determination of reactor

_ vessel exposure in terms of both neutron fluence (E > 1.0 Me V) and iron displacements per atom; 3 - Establish a methodology for the projection of exposure gradients through the thickness of the reactor vessel wall; and 4 - Provide a long term continuous neutron monitoring capability for the beltline region of the reactor vessel.

This report provides the results of the cavity neutron dosimetry evaluations performed for Fuel Cycle 8 and Fuel Cycle 9 irradiations and the replacement 290 degree in-vessel dosimetry capsule irradiated in Fuel Cycle 9. Fast neutron exposure in terms of fast neutron fluence (E > l .O Me V) and dpa is determined for all measurement locations in the reactor cavity as well as within the 1-4

replacement wall capsule. _The analytical formalism describing the relationship among the measurement points and locations within the reactor vessel wall is described and used to project the vessel exposure for Cycles 8 and 9. Uncertainties associated with the derived exposure parameters at the measurement locations and with the projected exposure of the reactor vessel are also provided .

1-5

Section 2 Description of the Measurement Program 2-1. Description of Reactor Cavity Neutron Dosimetry The Reactor Cavity Neutron Measurement Program employs advanced sensor sets that are recommended by and are designed to the latest ASTM neutron dosimetry standards. A listing of rthese ASTM standards is provided in Section 10.

The sensor sets consist of the following encapsulated dosimeters and gradient chains. Table 2-1 lists the neutron reactions that are of interest.

1. Radiometric Monitors (RM) - these include cadmium shielded foils of the following metals: iron, nickel, copper, titanium, niobium, and cobalt-aluminum. Cadmium shielded 238 237 fast fission reactions include U in paired uranium detectors (PUD) and Np in

2.

vanadium encapsulated neptunium oxide detectors. Bare iron and cobalt monitors are also included.

Gradient Chains - these stainless steel bead chains connect the dosimeter capsules containing radiometric monitors. Coupled with chemical analysis these segmented chains provide iron, nickel, and cobalt reactions which are used to complete the determination of the axial and azimuthal gradients between the discrete locations chosen for spectrum determinations.

The sensor sets are located in the annular space between the reactor vessel and the primary biological shield to characterize the neutron spectrum within the beltline region of the reactor vessel.

Placement of the multiple foil sensor sets was such that spectrum determinations could be made at various locations at an axial elevation representative of the midplane of the reactor core to measure spectrum changes caused by varying amounts of water located between the core and the reactor vessel. These thickness changes are due to the stair step shape of the reactor core

periphery relative to the cylindrical geometry of the reactor internals and vessel. Additional sensor sets are positioned opposite the bottom of the active core at the azimuthal angle of a longitudinal reactor vessel weld (270 degrees) and at the particular azimuthal angle (290 degrees) of an in-vessel surveillance capsule. Here the intent was to measure variations in neutron spectra 2-1

over the core height. . At each of the azimuthal locations selected for core midplane spectrum measurements, stainless steel gradient chains extended over the bottom half of the active fuel.

Additional stainless steel gradient chains were placed at symmetric locations in other quadrants to confirm the symmetry of the neutron flux distribution. These additional gradient chains extend over nearly the full height of the active fuel (except for the bottom-most nine inches) and extend up past the reactor vessel support structure.

2-2. Sensor Placement in the Reactor Cavity A detailed description of the cavity dosimetry hardware and plant specific. installation can be found in References 1 and 2. However, the following information is provided in this report to orient the reader to the plant geometry and the specifics of the sensor sets.

The placement of the individual multiple foil sensor sets and gradient chains within the Palisades reactor cavity is given in Table 2-2 for the Cycle 8 dosimetry and in Table 2-3 for the Cycle 9

dosimetry. The first five and the twelfth gradient chains are located in the annular gap between the reactor vessel insulation and the primary biological shield at a nominal radius of 108 inches relative to the reactor centerline and are supported from the reactor cavity seal drip pan. The remaining six gradient chains, which also support the sensor sets, are hung from an aluminum support bar also at a nominal radius of 108 inches relative to the reactor centerline. This bar is, in turn, supported from the drip pan. Refer to Figure 2-1 for a description of the reference coordinate system for the reactor cavity neutron dosimetry. Note that it has been determined that the dosimetry support bar is skewed radially (the 270 degree end of the bar is closer to the reactor vessel) and shifted six degrees clockwise as shown in Figure 2-1. Refer to Section 6 for additional information.

2-3. Description of Reactor Cavity Irradiation Capsules The sensor sets used to characterize the neutron spectra within the reactor cavity were contairied in 3.87 inch x 1.00 inch x 0.50 inch rectangular aluminum 6061 capsules. Each capsule included three compartments to hold the neutron sensors. The top compartment (position 1) contained the

bare radiometric monitors, whereas, the two remaining compartments (positions 2 and 3) held cadmium shielded packages. The separation between positions 1 and 2 was such that cadmium shields inserted into position 2 did not introduce any significant perturbation in the thermal flux in position 1. Aluminum 6061 was selected for the dosimeter capsules in order to minimize 2-2

neutron flux perturbations at the sensor set locations as well as to limit the radiation levels associated with post-irradiation shipping and handling of the capsules. A summary of the contents of the multiple foil capsules used during the Cycle 8 and Cycle 9 irradiations is provided in Appendix A.

2-4. Description of Reactor Cavity Gradient Chains Along with the multiple foil sensor sets placed at discrete locations within the reactor cavity, gradient chains were employed to obtain axial variations of fast neutron exposure along each of the twelve traverses. Subsequent to irradiation these gradient chains were removed from the cavity and segmented to provide neutron reaction rate measurements at six inch intervals over the height of the axial traverses. These gradient chains consisted of Type 304 stainless steel 0.188 inch diameter bead chain. When coupled with a chemical analysis, the stainless steel 54 yielded activation results for the Fe(n,p )54 Mn, 58 Ni(n,p )58 Co, and 59 Co(n;y) 6°Co reactions. The high purity iron, nickel, and cobalt-aluminum foils CC?ntained in the multiple foil sensor sets.

provided a direct correlation with the measured reaction rates from the stainless steel chain, and

also provided an overcheck on the chemical analysis of the type 304 steel. The results of the chemical analysis of the gradient chains is provided in Appendix A.

2-5. Description of In-Vessel Dosimetry Capsule ABB Combustion Engineering Nuclear Power manufactured and installed an In-vessel Dosimetry Capsule [11] which replaced the previously removed W-290 surveillance capsule. This dosimetry capsule was irradiated during Cycle 9. The in-vessel dosimetry capsule has the same external configuration as the existing Palisades surveillance capsules with minor design modifications to facilitate remote installation. The in-vessel dosimetry capsule assembly is shown in Figure 2-2.

The contents of each type of compartment is shown in Figure 2-3. The capsule compartments contain three sets of neutron dosimeters. No mechanical test specimens are included.

Neutron dosimeters are provided in three compartments in the capsule assembly so that an axial flux profile can be determined. The height of each set of neutron dosimeters relative to the core midplane is given in the table below. The designation includes a "U" or "L" indicating the upper

(four-hole) or lower (five-hole) location in the compartment. The upper part of a dosimeter compartment contains bare cobalt-aluminum, titanium, and iron wires and a bare vanadium encapsulated uranium oxide dosimeter. The lower part of a dosimeter compartment contains 2-3

cadmium shielded cobalt-aluminum, nickel, and copper wires and cadmium shielded vanadium encapsulated uranium oxide and neptunium oxide dosimeters. Thus each dosimeter compartment contains nine dosimeters. To prevent the cadmiumfrom interacting with the dosimeter material, each cadmium shielded dosimeter was first encapsulated in vanadium tubing before being inserted .

into the cadmium tubing. The uranium oxide and neptunium oxide were vanadium encapsulated during manufacture. All of the dosimeters were enclosed in grooved stainless steel tubing which identifies the dosimeter and facilitates handling. A summary and photographs of the dosimeters are provided in Appendix A.

Height of In-Vessel Neutron Dosimeters Height Relative to the Designation of Dosimeter Set Core Midplane (inches) lAlF-U +48.0 lAlF-L +42.0 lA4F-U +13.2 1A4F-L +7.2 lA7F-U -21.5 1A7F-L :.21.s 2-4

Table 2-1 Measured Neutron Reactions Neutron Dosimeter Gradient Reaction of Energy Product Capsule Chain or Material Interest Response<a) Half-Life Position<b)

Wire<c>

Copper 63 Cu(n,a) 6°Co 6.13-11 MeV 5.271 yr 2-Cd No Titanium . 46Ti(n,p )46 Sc 3.86-9.4 MeV 83.81 dy 2-Cd No Iron 54Fe(n,p )54Mn 2.47-7.8 MeV 312.5 dy 1-B and Yes 2-Cd Nickel 58 Ni(n,p )58 Co 2.09-7.6 MeV 70.82 dy 2-Cd

Yes Niobium<d) 93Nb( n,n')93mNb 0.67-5.7 MeV 16. l yr 2-Cd No Cobalt-Al 59 Co(n, y)6°Co Thermal 5.271 yr 1-B and Yes 2-Cd 23su 23sU(n,f)131Cs 1.51-6.7 MeV 30.17 yr 3-Cd No 231Np 237Np(n,f)mCs 0.67-5.7 MeV 30.17 yr 3-Cd No Notes:

a) . Energies between which 90% of activity is produced (235U fission spectrum) b) B denotes bare and Cd denotes cadmium.shielded c) Determined with additional chemical analysis d) Results of evaluati_ng niobium dosimeters are not included in this report.

2-5

Table 2-2 Azimuthal Locations for Palisades Cycle 8 Reactor Cavity Measurements Reference First Bar Azimuthal Octant Shifted Location<a> Equivalent Angle Description<c> ID Tag 30 deg 30 deg Gradient Chain Only 30 90 deg 0 deg

Gradient Chain Only 90 150 deg 30 deg Gradient Chain Only None 210 deg 30 deg Gradient Chain Only 210 260 deg 10 deg Gradient Chain Only None 270 deg 0 deg 6 deg Gradient Chain plus Capsules A and c<d> 270 280 deg 10 deg 16 deg Gradient Chain plus Capsule B 280 290 deg 20 deg 26 deg Gradient Chain plus Capsules D and E 290 300 deg 30 deg 36 deg Gradient Chain plus Capsule f<ct> 300 315 deg 45 deg 39 deg Gradient Chain plus Capsule G 315 330 deg 30 deg 24 deg Gradient Chain Only 330 340 deg 20 deg Gradient Chain Only 150 Notes:
a) Reactor coordinate system angles advance clockwise and 150 degrees is containment due north (Refer to Figure 2-1).
b) The dosimetry support bar has been determined to be shifted six degrees relative to the planned reference azimuthal location [14].
c) Capsules C and E are located 66 inches below the core midplane. The remaining
d) capsules are located on the core midplane.
The dosimetry installed at reference angles 270 and 300 degrees was not removed at the end of Cycle 8 [2].
2-6
Table 2 Azimuthal Locations for Palisades Cycle 9 Reactor Cavity Measurements Reference First - Bar Azimuthal Octant Shifted Location(al Equivalent Angle Description<cl ID Tag 30 deg 30 deg Gradient Chain Only S-2 30 90 deg 0 deg Gradient Chain Only S-2 90 150 deg 30 deg Gradient Chain Only S-2 150 210 deg 30 deg None Installed 260 deg 10 deg Gradient Chain Only S-2 260 270 deg 0 deg 6 deg* Gradient Chain plus Capsules A and CC<l> 270 280 deg 10 deg 16 deg Gradient Chain plus Capsule J S-2 280 290 deg 20 deg 26 deg Gradient Chain plu*s Capsules K and L S-2 290 300 deg 30 deg 36 deg Gradient Chain plus Capsule pdl 300 315 deg 45 deg 39 deg Gradient Chain plus Capsule N S-2 315 330 deg 30 deg 24 deg Gradient Chain Only S-2 330 340 deg 20 deg Gradient Chain Only S-2 340 Notes:
a) Reactor coordinate system angles advance clockwise and 150 degrees is containment due north (Refer to Figure 2-1).
b) The. dosimetry support bar has been determined to be shifted six degrees relative to the planned reference azimuthal location [14] .
c) . Capsules C and L are located 66 inches below the core midplane. The remaining d) capsules are located on the core midplane.
The dosimetry installed at reference angles 270 and 300 degrees was not removed at the end of Cycle 8 [2],
2-7
Figure 2-1 Consumers Power Company Palisades Nuclear Plant Reactor Cavity Neutron Dosimetry Reference Coordinate System 260° 210° Inlet Outlet 180° 150°
Outlet Inlet Fuel North
Transfer Tube Note: The dosimetry bar has been determined to be shifted six degrees clockwise relative to the position shown above.
2-8
Figure 2-2
- Consumers Power Company Palisades Nuclear Plant In-Vessel Dosimetry Capsule Assembly Lock Assembly Wedge Coupling Assembly Extension Assembly FLUX CAPSULE ASSEMBL y __..,.,
lAlF FILLER CAPSULE ASSEMBLY FLUX CAPSULE ASSEMBLY 1A4F FILLER CAPSULE ASSEMBLY FLUX CAPSULE ASSEMBLY - -
1A7F 2-9
Figure 2-3 Consumers Power Company Palisades Nuclear Plant In-Vessel Dosimetry Capsule Compartment Assemblies FLUX CAPSULE ASSEMBLY FILLER CAPSULE ASSEMBLY FILLER CAPSULE ASSEMBLY
..*.* .:f/V,
/,,. -
-~~-Piil
%{-
~
FLUX CAPSULE ASSEMBLY 2-10
Section 3 Neutron Transport and Dosimetry Evaluation Methodologies 3-1. Neutron Transport Analysis Methods Fast neutron exposure calculations for the reactor and cavity geometry were carried out for Cycles 8 and 9 using discrete ordinates transport techniques. These calculations provided the energy distribution of neutron flux for use as input to neutron dosimetry evaluations as well as for use in relating measurement results to the actual exposure at key locations in the reactor vessel wall.
A plan view of the calculational model of the reactor geometry at the core midplane elevation is shown in Figures 3-1 through 3-3. Due to the radial extent of the geometry modelled and in order to keep a fine spatial mesh definition, the calculation was carried out in two parts as shown in these figures. The inner part of the model encompassed the fuel region and the ex-core region
through the water inside the reactor vessel. Figure 3-1 shows the inner region for Cycle 8 which had two stainless steel pin regions that replaced fuel pins. The Cycle 9 fuel geometry did not have these regions as shown in Figure 3-2. The outer part of the model utilized the boundary source for each cycle calculated in the inner part of the model at the inside of the barrel to calculate the neutron transport from the barrel through the reactor vessel and cavity and into the biological shield. The outer part of the model was identical for Cycle 8 and Cycle 9.
Since the reactor exhibits 1/8 core symmetry only a 0 to 45 degree sector is depicted in the figures. In addition to the core, reactor internals, reactor vessel, and the primary biological shield, the model also included explicit representations of a surveillance capsule attached to the vessel wall at 20 degrees, the vessel cladding, and the mirror insulation located external to the vessel. From a neutron transport standpoint, the inclusion of the surveillance capsules and associated support structures in the analytical model is significant for analysis of capsule dosimetry results and evaluation of capsule exposures. To a lesser extent, the capsules impact the reactor vessel exposure at locations close to the capsule.
In contrast to the relatively massive stainless steel structures associated with the internal
surveillance capsules, the small aluminum capsules used in the reactor cavity measurement program were designed to minimize perturbations in the neutron flux and, thus, to provide free field data at the measurement locations. Therefore, explicit modeling of these small capsules in the transport model was not required.
3-1
The transport calculations for each of the two parts of the reactor model depicted in Figures 3-1
through 3-3 were carried_ out in R,8 geometry using the DOT-UIW two-dtinensional discrete ordinates transport theory code [12] and the SAILOR cross-section library [13]. The SAILOR library is a 47 neutron energy group ENDF-B/IV based data set produced specifically for light water reactor applications. In these analyses, anisotropic scattering was treated with *a P, expansion of the cross-sections and the angular discretization was modeled with an S 16 order of angular quadrature. The S 16 quadrature was used to get an improved calculation of the flux shape in the reactor cavity to eliminate a large part of the uncertainty due to neutron streaming. The S8 calculational error due to the streaming in the relatively large Palisades reactor cavity was estimated to be as large as five percent [ 15]. The use of the increased number of angles represents an improvement over the previous analysis of the Cycle 8 dosimetry and therefore the Cycle 8 dosimetry analyses [14] have been repeated with the updated data. The change in the input spectrum was found to have less than a one percent effect on the FERRET analysis results for the fast neutron flux and the iron atom displacement rate.
Additional geometry changes were made to the model used for the calculations previously*
reported [14]. These changes were made as a result of the uncertainty studies [15], where it was found that the best estimate of the mean vessel thickness should be increased by 0.25 inches (0.635 cm). The inner radius of the reactor vessel was left unchanged at the noni.inal value.
Additional radial mesh points were also add~d to the reactor cavity portion of the model to better define the flux at the dosimetry locations. The dimensions in the revised model are indicated in Figure 3-3.
The changes in the model preclude an exact comparison between the S8 and S 16 calculational results, but a comparison of the flux traverses in the reactor cavity indicates that the increased number of angles made only minor changes in the calculated fast neutron flux (E > LO MeV).
Relative flux values agree between the two calculations to within about three percent in the cavity. It is concluded that the improvement gained does not indicate that S16 calculations are required to achieve adequate results for reactor cavity fast neutron flux calculations.
It should also be noted that, due to the longer calculational time for the S16 flux determination,
the calculation only included the energy-groups above 0.-1 MeV. This cutoff was chosen because only a small fraction (about three percent at the reactor vessel inner radius) of the damage to the vessel (as indicated by the iron dpa cross section) is caused by neutrons below this energy.
Neutron flux values for the energy groups below 0.11 MeV were generated by using the previous S8 calculations normalized in the region from 0.11 to 1.0 MeV.
3-2
The transport calculations were normalized to the axial peak power location and for operation at a thermal power level of 2530 MWt. . The spatial core power
. distributions utilized in the calculation were supplied by Consumers Power [ 16, 17]. They were used to determine the neutron source time-averaged over the actual operation for each fuel cycle. The power distributions were supplied as a pin-by-pin power distribution for each of the outer fuel assemblies and as cycle burnups for each fuel assembly. The neutron source was derived for each fuel pin and for each fuel assembly using burnup dependent values of the fission neutron energy spectrum, neutrons per fission, and energy per fission evaluated at the mean assembly burnup value. The source spectrum was calculated by determining the fraction of fissions occurring in each of the important uranium and plutonium isotopes for the mid-cycle burn up and calculating a resultant average fission spectrum using the ENDF-B/V fission spectrum for each isotope.
To obtain. the source normalized to the axial peak location, axial peaking factors were entered for each fuel assembly. For the 15 outer assemblies in the reactor octant, these factors ranged from 1.055 to 1.135 with an average of 1.093 for Cycle 8, and from 1.071 to 1.154 with an*
average of 1.124 for Cycle 9. Since. almost all the assemblies peaked near the same axial position, the peak po_\Ver for all assemblies was used, and the calculation therefore represents the fluence at the maximum axial point as if the entire core was at that peak power.
For Cycles 8 and 9 in the Palisades Plant, the average axial peak for the outer fuel assemblies is about 30 inches below the core midplane based on the fuel power calculatfons. The power at the midplane is indicated to be within two percent of this maximum value. In the measurements presented in Section 6 it is seen that the measured neutron flux peaks around the midplane but orily a small difference exists between the midplane and 30 inches below the midplane. For the
purposes of this analysis, therefore, the midplane location, the region between the midplane and
-30 inches, and the location of the beltline circumferential weld will all be assumed to be at the axial peak fast neutron flux.
The source from each fuel assembly was spatially located to take into account the varying gaps between fuel-assemblies and thus represents the location of source from each pin as accurately as possible. The source was converted from the X-Y pin geometry to the R-8 DOT geometry by distributing the source over a square area equal to the pitch for each pin. This area was then divided into a 10 x 10 array, each source element of which was placed into the DOT mesh containing the center point of the source element. The error in source positioning, both radial and azimuthal, was thus kept to less than +/-0.07 cm for each of these source elements. Averaging the error over a very large number of source elements produces an extremely small resultant bias
in source positioning. Thus the error due to the geometry conversion can be assumed to be negligible. The neutron source was input to the DOT calculation for the inner part of the model as a 47 group fixed source for each DOT spatial mesh point in the fuel region.
Details of fuel assembly locations, core geometry, and other reactor parameters (except for the vessel thickness as noted above) were taken from Reference 18. Since the Palisades Plant operated at a reduced power of 80 percent for most of Cycle 8, a cycle-specific reactor coolant bypass water temperature of 558 °F was used [ 16], instead of the standard value of 560 °F used for previous cycles. For Cycle 9 the value of 560 °F was used. Recent information indicates that, since the new steam generators were installed, the bypass water temperature is 555 to 557 °F. This temperature difference will result in the calculation being biased high by one to three percent.
The results of the DOT calculations are presented in Section 4 .
3-2. Neutron Dosimetry Evaluation Methodology The use of passive neutron sensors such as those included in internal surveillance capsules and reactor cavity dosimetry sets does not yield a direct measure of the energy dependent neutron flux level at the measurement location. Rather, the activation or fission process is a measure of the integrated effect that the time- and energy-dependent neutron flux has on the target material over the course of the irradiation period. An accurate assessment of the average flux level and, hence, time integrated exposure (fluence) experienced by the sensors may be developed from the measurements only if the sensor characteristics and the parameters_ of the irradiation are well known. In particular, the following variables are of interest:
l - The measured specific activity of each sensor; 2 - The physical characteristics of each sensor; 3 - The operating history of the reactor; 4 - The energy response of each sensor; and 5 - The neutron energy spectrum at the sensor location.
In this section the procedures used by Westinghouse to determine sensor specific activities, to develop reaction rates for individual sensors from the measured specific activities and the operating history of the reactor, and to derive key fast neutron exposure parameters from the measured reaction rates are described.
3-4
Following each irradiation, the multiple foil sensor sets and gradient chains were recovered from the Palisades reactor and transported to Pittsburgh for evaluation. All analysis of the radiometric foils and gradient chains was performed at the Westinghouse Analytical Services Laboratory at Waltz Mill.
The specific activity of the radiometric sensors and gradient chain segments was determined using established ASTM procedures [9, 19 through 30]. Following sample preparation and weighing, the specific activity of each sensor was determined by means of a lithium drifted germanium, Ge(Li), gamma spectrometer. For the stainless steel gradient chains used in the cavity irradiations, individual sensors were obtained by cutting one inch long pieces out of the chains at six inch intervals. For the long gradient chains, the data points span an axial interval from 4.5 feet below the core midplane to 8.0 feet above the core midplane. For the short gradient chains, which are attached to the support bar, the data points span an axial interval from 5.5 feet below the core midplane to 0.5 feet above the core midplane.
The irradiation history of the reactor for Cycles 8 and 9 was supplied by Consumers Power"
[31,32]. These data were supplied as monthly thermal power generation figures. For the sensor
sets utilized in. surveillance capsule and reactor cavity irradiations, the half-lives of the product isotopes are long enough that a monthly histogram describing reactor operation has proven to be an adequate representation for use in radioactive decay corrections for the reactions of interest in the exposure evaluations.
Having the measured specific activities, the operating history of the reactor, and the physical characteristics of the sensors, reaction rates referenced to full power operation are determined from the following equation:
A R =
where:
R = reaction rate averaged over the irradiation period and referenced to operation at a core thermal power level of Pref (rps/nucleus),
A = measured specific activity (disintegrations per second per gram),
No = number of target element atoms per gram of sensor, F = weight fraction of the target nuclide in the sensor material, y = number of product atoms produced per reaction, pj = average core thermal power level during irradiation period j (MWt),
3-5
Pref= maximum or-reference core thermal power level of the reactor (MWt),
Ci = - calculated ratio of <j> (E> LO MeV) at full power during irradiation period j to the time weighted average <j> (E > 1.0 MeV) at full power over the entire irradiation period, A = decay constant of the product nuclide (sec- 1),
ti = . length of irradiation period j (sec), and td - decay time following irradiation period j (sec).
The summation is carried out over the total number of monthly intervals comprising the total irradiation period.
In the above equation, the ratio Pi I Pref accounts for month by month variation of power level within any giveri fuel cycle as well as over multiple fuel cycles. The ratio Ci, which was calculated for each fuel cycle using the transport technology described above, accounts for the change in sensor reaction rates caused by variations in flux level induced by changes in core spatial distributions from fuel cycle to fuel cycle.
The ratio Ci was taken to be unity for the evaluation over a single fuel cycle and is .the relative flux (E > 1.0 MeV) at_ the dosimetry location for multicycle irradiations.
Prior to using the measured reaction rates in the least squares adjustment procedure discussed ~n 238 235 Section 3-3 of this report, corrections were made to the depleted U foils (400 ppm U) to account for the presen~e of 235 U impudties in the sen_sors. These corrections were made based on use of the data measured on natural uranium foils located in the same foil packet. Corrections ranged from 3 to 14 percent depending on the specific fission product and the sensor set location.
237 Additional corrections were also made to the Np results to account for internal gamma ray_
absorption (two percent). All foils in the bottom sets (Capsules E, C, and L) were corrected to the center of the capsule position (nominal 66 inches below core midplane) using local axial 54 54 58 58 gradients measured for Fe (n,p) Mn and Ni (n,p) Co (fast neutron reactions) and 59 6 Co (n;y) °Co (thermal and epithermal neutron reactions);
3-3. Least Squares Adjustment Procedure Values of key fast neutron exposure parameters were derived from the measured reaction fates using the -FERRET least squares adjustment code [33]. The FERRET approach used the measured reaction rate data and the calculated neutron energy spectrum at the sensor set locations as input and proceeded to adjust the a priori (calculated) group fluxes to produce a best fit (in 3-6
a least squares sense) to the reaction rate data .. The exposure parameters along with their associated uncertainties were then obtained from the adjusted spectra.
In the FERRET evaluations, a log-normal least-squares algorithm weights both the a priori values and the measured data in accordance with the assigned uncertainties and correlations. In general, the measured values fare linearly related to the flux ¢ by some response matrix A:
ft (s,11> =*L A~> 4>~11>
g where:
i indexes the measured values belonging to a single data set s, g designates the energy group, and a designates spectra that may be simultaneously adjusted:
For example,
relates a set of measured reaction rates Rik to a single spectrum ¢kg by the multigroup cross-section crig where k designates a particular neutron spectrum. (In this case, FERRET also adjusts the cross-sections.) The log-normal approach automatically accounts for the physical constraint of positive fluxes, even with large assigned uncertainties.
In the FERRET analysis of the dosimetry data, the continuous quantities (i.e., fluxes and cross-sections) are approximated in 53 energy groups. The calculated fluxes (a priori input) are expanded into the FERRET group structure using the SAND-II code [34]. This procedure is carried out by first expanding the a priori spectrum into the SAND-II 620 energy group structure using a spline interpolation procedure for interpolation in regions where grpup boundaries do not coincide.
The 620 group spectrum is then easily collapsed to the group structure used in FERRET.
The cross-sections were also collapsed into the 53 energy group structure using SAND-II with the calculated spectrum (as expanded to 620 groups) as weighting function. The cross sections were taken from the ENDF-BN dosimetry file. Uncertainty estimates in the form of 53 x 53 covariance matrices have been constructed for each cross-section based on the ENDF-B/V files.
Correlations between cross-sections for different reactions are neglect~d due to data and code limitations, but this omission does not significantly impact the results of the adjustment.
3-7
For each set of data or a priori values, the inverse of the corresponding relative covariance matrix M is used as a *statistical weight. In some cases, as for the cross-sections, a multigroup covariance matrix is used. More often, a simple parameterized form is employed:
where en specifies an overall fractional normalization uncertainty (i.e., complete correlation) for the corresponding set of valu~s. The fractional uncertainties rg specify additional random uncertainties for group g that are correlated with a correlation matrix:
Pggl -- (1 - 6) Ugg/
+ e eTn-['(g-g')
,t" 2
]
' 2y2 The first term specifies purely random uncertainties while the second term describes short-range correlations over a range y (0 specifies the strength of the latter term). The value of 8 is l when g equals g' and 0 otherwise.
For the a priori calculated fluxes, a short-range correlation of y =6 groups was used. This choice implies that neighboring groups are strongly correlated when 0 is close to 1. Strong short-range correlations (or anticorrelations) were justified based on information presented by R.E. Maerker [35]. Maerker's results are closely duplicated when y = 6.
For the integral reaction rate covariances, simple normalization and random uncertainties were combined as deduced from experimental uncertainties. The reaction rate uncertainty estimates include both a statistical (counting) uncertainty and systematic uncertainty. The latter is based
. on known errors such as uncertainty in counter efficiency, unknown errors that are derived from consistency of counting results, and estimates of error arising . from the power history and corrections for competing reactions. Specific discussion of these uncertainty contributors may be found in Reference 15 .
3-8
In performing least squares adjustments with the FERRET code, the neutron flux spectrum calculated at the center of the dosimetry location is input to the analysis. Typical uncertainties in the input (a prfrJri) spectra and the measured reaction rates used in the FERRET evaluations are as follows:
Flux Normalization Uncertainty (en) 30 percent Flux Group Uncertainties (rg)
(E > 0.0055 MeV) 30 percent (0.68 eV < E < 0.0055 MeV) 58 percent (E < 0.68 eV) 104 percent Short-Range Correlation Strength (8)
(E > 0.0055 MeV) 0.9 (0.68 eV < E < 0.0055 MeV) 0.5 (E < 0.68 eV) 0.5 Flux Group Correlation Range (y)
(E > 0.0055 MeV) 6 (0.68 e V < E < 0.0055 Me V) 3 (E < 0.68 eV) 2 I Reaction Rate Uncertainty 5-10 percent It should be noted that the uncertainties listed for the upper energy ranges extend down to the lower range. For example, the 58 percent group uncertainty in the second range is made up of a 30 percent uncertainty with a 0.9 short-range correlation and a range of six groups, and a second part of magnitude 50 percent with a 0.5 correlation and a range of three groups that represents* additional uncertainty on the spectrum shape in the resonance region. Of cour.se for problems with threshold reaction rate measurements, the resonance region analysis does not affect the high energy neutron flux result. These input uncertainty assignments were based on prior
experience in using the FERRET least squares adjustment approach in the analysis of neutron dosimetry fro,m surveillance capsule, reactor cavity, and benchmark irradiations. The values are liberal enough to permit adjustment of the input spectrum to fit the measured data for all practical applications.
3-9
Figure 3-1 Reactor Geometry Showing a 45 Degree R,O Sector for the Inner Part of the Model for Cycle 8 I
l 4(}j.
121
Vl 101 SS PINS c::
LU 80 FUEL f-REGION LU f-z LU u
60 SHROUD 40 20 SS _ _-+-
. PINS OL---~-~L---~~--------.-.-.1--.J..L...+~~-:-'-~l9~6:--~
76 96 116 136 156 176 RADIUS IN CENTIMETERS 3-10
Figure 3-2 Reactor Geometry Showing a 45 Degree R,8 Sector for the Inner Part of the Model for Cycle 9 I
140 120 100 V1 c:: 81)
La.I
~
FUEL La.I
~
~
z:
La.I u
REGION 60 SHROUD
.40 20 oL....~_:..-+-_J~--~~--~~""""-:~___J~~---1.-~---.1 76 96 116 136 156 176 196 RADIUS IN CENTIMETERS 3-11
* -Figure 3-3 Reactor Geometry Showing a 45 Degree R,8 Sector for the Outer Part of the Model for Cycles 8 and 9 250 225 200
~j'~
~9'(:I "6:'6'
~9'/ *.s: \
175 ~,,
.!)
o, STEEL CONCRETE o> *a(SI
~,, LINER SHIELD
9.
9
V'I 150 c::
LI.I I-
- 125 LI.I
c I-z LI.I u
100 75 0 REACTOR 20 CAVITY CAPSULE so 25 AIR GAP 0
135 160 185 210 235 260 285 310 335 360 RADIUS IN CENTIMETERS 3-12
Section 4 Results of Neutron Transport Calculations As noted in Section 3 of this report, the data from the cycle specific neutron transport calculations were used in evaluating dosimetry from the reactor cavity and in-vessel irradiations as well as in relating the results of these evaluations to the neutron exposure of the reactor ves.sel wall. In this section, the key data extracted from the calculation are presented and their relevance to the dosimetry evaluations and reactor vessel exposure projections is discussed.
4-1. Reactor Cavity Sensor Set Locations The data from the Cycle 8 and Cycle 9 transport calculations which are needed for the reactor cavity sensor evaluations are provided in Tables 4-1 and 4-2. Specifically, the calculated neutron energy spectra are listed for dosimetry locations at 6, 16, 26, and 39 degrees relative to the core cardinal axes, at axial midplane, and at radial locations in *the cavity corresponding to the
dosimetry position as described in Section 2. Table 4-1 gives the three spectra used for analysis of the Cycle 8 dosimetry and Table 4-2 gives the spectra used for the dosimetry removed after Cycle 9. In Table 4-2, the spectrum at 6 degrees is a weighted average of Cycles 8 and 9 (weighted by the effective full-power time) since the dosimetry at this arigle was irradiated for both cycles. The data in these two tables are the a priori spectra used as the starting guess in the FERRET least squares adjustment evaluations of the cavity sensor sets. On a relative basis these calculated energy distributions establish a baseline against which adjusted spectra may be compared. It should be noted that the groups below 0.11 Me V were not calculated using the S 16 quadrature and the values in Tables 4-1 and 4-2 for the lower energy groups were determined by normalizing the previous Cycle 8 calculation [14] to the S 16 flux in the energy range 0.1 to 1.0 MeV.
4-2. In-Vessel Dosimetry Capsule Neutron flux-spectrum data for the analysis of the in-vessel dosimetry capsule for Cycle 9 is given in Table 4-3. This data is the calculated spectrum at the center of the capsule at an
azimuthal location of 20 degrees (symmetric to the actual location of 290 degrees), and a radial location of 215.43 cm.
4-1
4~3. Reactor Vessel Wall -
The data from the Cycles 8 and 9 calculations pertinent to the reactor vessel wall are provided in Tables 4-4 through 4-14. In Table 4-4, thecalculated azimuthal distribution of fast neutron flux (E > 1.0 MeV) is listed for the reactor vessel clad/base metal interface (219.075 cm radius) for each of the two cycles and for the weighted average of the two cycles. The flux at this radius (base metal inner radius) for each angle was obtained by interpolation between the two mesh points in the transport calculation that radially bracket this location; these points are the center of the vessel cladding (218.757 cm radius), and the center of the first mesh interval in the base*
metal (219.392 cm radius). In the detailed tabulation in Table 4-4, calculated flux levels are given for each of the 61 azimuthal mesh intervals included in the analytical model.
Table 4-5 shows the calculated azimuthal distribution of fast neutron exposure parameters in terms of fast neutron flux (E > 1.0 Me V) and (E > 0.1 Me V), and iron atom displacement rate (dpa/sec) at 5 degree intervals over the reactor geometry. These data are also interpolated to the
. reactor vessel clad/base metal interface, Also given in Table 4-5 are the exposure rate ratios*
[~ (E > 0.1 MeV)] I[~ (E > 1.0 MeV)] and [dpa/sec] I[~ (E > 1.0 MeV)] that provide an indication of the small variation in the fast neutron spectrum as a function of azimuthal angle at the reactor vessel inner radius.
Radial gradient information for the fast neutron flux (E > 1.0 ~e V) and (E > 0.1 Me V), and the iron atom displacement rate (dpa/sec) is given in Tables 4-6 through 4-14 .. Calculated data are presented for Cycle 8, Cycle 9, and a weighted average of the Cycle 8 and Cycle 9 calculations.
The gradients are presented on a relative basis for each exposure parameter at the 0, 15, 30; and 45 degree azimuthal locations. Exposure rate distributions within the reactor vessel wall can be obtained by normalizing the calculated or projected exposure at the reactor vessel in:ner radius
. to the gradient data given in Tables 4-6 through 4-14..
4-2
Table 4-1 Calculated Neutron Energy Spectra At Cavity Sensor Set Locations for Cycle 8
, Lower Neutron Flux (n/crn 2 -sec)
Energy Azimuthal Angle (MeV) 16 deg 26 deg 39 deg l.42E+Ol 3.128E+05 2.604E+05 2.032E+05 l.22E+Ol l.301E+06 l.074E+06 8.325E+05 l.OOE+Ol 4.257E+06 3.408E+06 2.556E+06 8.61E+OO 7.702E+06 6.086E+06 4.506E+06 7.41E+OO l.169E+07 9.103E+06 6.640E+06 6.07E+OO 2.424E+07 l.867E+07 l.351E+07 4.97E+OO 2.919E+07 2.238E+07 l.620E+07 3.68E+OO 4.927E+07 3.784E+07 2.747E+07 3.0lE+OO 4.315E+07 3.303E+07 2.426E+07 2.73E+OO 3.597E+07 2.740E+07 2.007E+07 2.47E+OO 4.411E+07 3.444E+07 2.544E+07 2.37E+OO 2.242E+07 l.751E+07 l.294E+07 2.35E+OO 7.792E+06 5.866E+06 4.175E+06 2.23E+OO 3.802E+07 2.924E+07 2.096E+07 1.92E+OO 9.102E+07 7.114E+07 5.219E+07 l.65E+OO l.460E+08 l.137E+08 8.227E+07 l.35E+OO 2.232E+08 l.778E+08 l.330E+08 l.OOE+OO 5.845E+08 4.670E+08 3.466E+08 8.21E-Ol 6.033E+08 4.868E+08 3.622E+08 7.43E-Ol 2.572E+08 2.194E+08 l.802E+08 6.08E-Ol l.278E+09 l.047E+09 7.934E+08 4.98E-Ol l.237E+09 l.037E+09 8.186E+08 3.69E-Ol l.307E+09 l.117E+09 9. l 19E+08
NOTE: The upper energy of the first energy group is 17.33 MeV 4-3
Table 4-1 (Continued)
Calculated Neutron Energy Spectra At Cavity Sensor Set Locations for Cycle 8 Lower Neutron Flux (n/cm 2-sec)
Energy Azimuthal Amde (MeV) 16 deg 26 deg 39 deg 2.97E-01 1.913E+09 l.617E+09 l.284E+09 l.83E-Ol 2.371E+09 2.107E+09 l.814E+09
l. l lE-01 2.664E+09 2.363E+09 2.024E+09 6.74E-02 l.790E+09 l.585E+09 I.392E+09 4.09E-02 l.373E+09 l.225E+09 l.093E+09 3.18E-02 4.318E+08 3.909E+08 3.590E+08 2.61E-02 l.965E+08 l.800E+08 1.689E+08
. 2.42E-02 8.032E+08 6.928E+08 5.675E+08
2.19E-02 l.50E-02
7. lOE-03 3.36E-03 5.714E+08 l.157E+09 l.195E+09
l. l 75E+09 4.962E+08 l.030E+09 l.091E+09 l.080E+09 4.126E+08 9.094E+08 l.017E+09 l.010E+09 l.59E-03 9.953E+08 9.157E+08 8.650E+08 4.54E-04 l.488E+09 l.373E+09 1.299E+09 2.i4E-04 7.512E+08 6.952E+08 6.631E+08 l.OlE-04 7.787E+08 7.091E+08 6.858E+08 3.73E-05 9.578E+08 8.861E+08 8.446E+08 l.07E-05 1.124E+09 l.040E+09 9.912E+08 5.04E-06 6.185E+08 5.727E+08 5.467E+08 l.86E-06 7.374E+08 6.834E+08 6.533E+08 8.76E-07 4.779E+08 4.434E+08 4.245E+08 4.14E-07 4.103E+08 3.8l1E+08 3.654E+08 l.OOE-07 7.570E+08 7.033E+08 6.748E+08 0.00 l.926E+09 l.786E+09 l.709E+09 4-4
Table 4-2 Calculated Neutron Energy Spectra At Cavity Sensor Set Locations for Cycle 9 Lower Neutron Flux (n/cm 2-sec)
Energy Azimuthal Angle (MeV) 6 deg" 16 deg 26 deg 39 deg l.42E+Ol 2.613E+05 2.541E+05 2.130E+05 1.63 IE+OS l.22E+Ol l.063E+06 l.024E+06 8.867E+05 6.543E+05 l.OOE+Ol 3.312E+06 3.199E+06 2.736E+06 l.964E+06 8.61E+OO 5.873E+06 5.680E+06 4.833E+06 3.440E+06 7.41E+OO 8.726E+06 8.442E+06 7.140E+06 5.046E+06 6.07E+OO l.773E+07 l.725E+07 l.453E+07 l.026E+07 4.97E+OO 2.100E+07 2.044E+07 l.720E+07 l.228E+07 3.68E+OO 3.495E+07 3.391E+07 2.857E+07 2.073E+07 3.0IE+OO 3.057E+07 2.958E+07 2.498E+07 l.829E+07 2.73E+OO 2.531E+07 2.452E+07 2.067E+07 l.5 I IE+07 2.47E+OO 3.140E+07 3.016E+07 2.563E+07 l.912E+07 2.37E+OO l.591E+07 l.530E+07 l.300E+07 9.722E+06 2.35E+OO 5.359E+06 5.250E+06 4.384E+06 3.142E+06 2.23E+OO 2.653E+07 2.574E+07 2.165E+07 l.574E+07 l.92E+OO 6.479E+07 6.210E+07 5.272E+07 3.914E+07 1.65E+OO l.037E+08 9.923E+07 8.401E+07 6.168E+07 l.35E+OO l.613E+08 l.527E+08 l.3l1E+08 9.944E+07 l.OOE+OO 4.238E+08 3.999E+08 3.433E+08 2.589E+08 8.21E-Ol 4.418E+08 4.136E+08 3.566E+08 2.703E+08 7.43E-Ol l.971E+08 l.796E+08 l.608E+08 l.335E+08 6.0SE-01 9.504E+08 8.795E+08 7.652E+08 5.907E+08 4.98E-Ol 9.357E+08 8.567E+08 7.574E+08 6.072E+08
3.69E-Ol l.003E+09 9.107E+08 8.157E+08 6.745E+08 NOTE: The upper energy of the first energy group is 17.33 MeV 4-5
Table 4-2 (Continued)
Calculated Neutron Energy Spectra.
At Cavity Sensor Set Locations for Cycle 9 Lower Neutron Flux (n/cm 2-sec)
Energy Azimuthal Angle (MeV) 6 dega 16 deg 26 deg 39 deg:
2.97E-Ol l.463E+09 l.328E+09 l.179E+09 9.513E+08 1.83E-Ol l.882E+09 1.673E+09 l.536E+09 l.336E+09
l. l lE-01 2. l 16E+09 l.878E+09 l.722E+09 l.491E+09 6.74E-02 l.435E+09 l.248E+09 l.156E+09 l.027E+09 4.09E-02 l.109E+09 9.569E+08 8.940E+08 8.065E+08 3.18E-02 3.627E+08 3.010E+08 2.852E+08 2.650E+08 2.61E-02 l.643E+08 l.370E+08 l.313E+08 L247E+08 2.42E-02 6.272E+08 5.598E+08 5.056E+08 4.189E+08 2.19E-02 4.517E+08 3.983E+08 3.621E+08 3.045E+08 l.50E-02 9.375E+08 8.067E+08 7.517E+08 6.712E+08
7. lOE-03 9.943E+08 8.328E+08 7.960E+08 7.504E+08 3.36E-03 9.811E+08 8.186E+08 7.879E+08 7.453E+08 l.59E-03 8.316E+08 6.937E+08 6.682E+08 6.384E+08 4.54E-04 l.245E+09 l.037E+09 l.002E+09 .9.588E+08 2.14E-04 6.302E+08 5.236E+08 5.073E+08 4.894E+08 1.0 IE-04 6.524E+08 5.428E+08 5.174E+08 5.061E+08 3.73E-05 8.022E+08 6.675E+08 6.466E+08 6.233E+08 l.07E-05 9.408E+08 7.835E+08 7.591E+08 7.315E+08 5.04E-06 5.177E+08 4.311E+08 4.179E+08 4.035E+08 l.86E-06 6.176E+08 5.140E+08 4.987E+08 4.822E+08 8.76E-07 4.007E+08 3.331E+08 3.235E+08 3.133E+08 4.14E-07 3.445E+08 2.860E+08 2.781E+08 2.696E+08 l.OOE-07 6.368E+08 5.276E+08 5.132E+08 4.980E+08 0.00 l.622E+09 l.342E+09 l.303E+09 l.262E+09
a. Weighted Average of Cycle 8 and Cycle 9 flux.
4-6
Table 4-3 Calculated Neutron Energy Spectra At the 290° Capsule Center for Cycle 9 Lower Neutron Lower Neutron Energy Flux Energy Flux 2
(MeV) (n/cm 2 -sec2 (MeY2 (n/cm -sec~
l.42E+Ol l.250E+07 l.83E-Ol 5.367E+09 l.22E+Ol 5.153E+07 1.l lE-01
4.711E+09 l.OOE+Ol l.996E+08 6.74E-02 3.814E+09 8.61E+OO 3.977E+08 4.09E-02 3.172E+09 7.41E+OO l.014E+09 3.18E-02 l.277E+09 6.07E+OO l.735E+09 2.61E-02 8.551E+08 4.97E+OO 2.441E+09 2.42E-02 8.1 l8E+08 3.68E+OO 4.199E+09 2.19E-02 6.085E+08 3.0lE+OO 2.900E+09 1.SOE-02 l.764E+09 2.73E+OO 2.113E+09 7.lOE-03 3.549E+09 2.47E+OO 2.336E+09 . 3.36E-03 3.965E+09 2.37E+OO 1.150E+09 1.59E-03 3.754E+09 2.35E+OO 2.988E+08 4.54E-04 5.858E+09 2.23E+OO l.434E+09 2.14E-04 3.423E+09 l.92E+OO 3.447E+09 l.OlE-04 3.578E+09 l.65E+OO 3.442E+09 3.73E-05 4.762E+09 l.35E+OO 4.574E+09 1.07E-05 5.894E+09 l.OOE+OO 6.317E+09 5.04E-06 3.480E+09 8.2lE-O1 3.827E+09 l.86E-06 4.490E+09 7.43E-Ol 2.027E+09 8.76E-07 3.207E+09 6.08E-01 4.377E+09 4.14E-07 2.997E+09 4.98E:.01 3.628E+09 l.OOE-07 8.436E+09 3.69E-01 4.081E+09 0.00 2.7947E+l0 2.97E-Ol 3.360E+09 NOTE: The upper energy of the first energy group is 17.33 MeV 4-7
Table 4-4 Azimuthal Variation of Fast Neutron Flux (E > 1.0 MeV)
At the Reactor Vessel Clad-Base Metal Interface An!!le (de!!} Cycle 8 Cycle 9 Cvcle 8-9 Av!!.
0.12 2.155E+ 10 2.082E+l0 2.124E+ 10 0.50 2.150E+l0 2.08lE+10 2.120E+ 10 l.25 2.155E+l0 2.082E+l0 2.124E+IO 2.25 2.224E+l0 2.106E+l0 2.174E+l0 3.25 2.337E+l0 2.145E+l0 2.255E+IO 4.25 2.491E+l0 2.198E+l0 2.366E+!O 5.37 2.695E+l0 2.269E+l0 2.513E+ 10 6.63 2.973E+l0 2.366E+l0 2.714E+IO 7.62 3.238E+l0 2.460E+l0 2.906E+!O 8.50 3.475E+l0 2.544E+10 . 3.077E+l0 9.50 3.748E+l0 2.641E+l0 3.276E+l0 10.50 4.017E+l0 2.739E+l0 3.47!E+10 11.50 4.266E+l0 2.831E+l0 3.653E+l0 12.50 4.485E+l0 2.914E+l0 3.814E+l0 13.50 4.667E+l0 2.983E+l0 3.948E+l0 14.50 4.801E+l0 3.033E+l0 4.046E+l0 15.50 4.880E+l0 3.061E+l0 4.103E+IO 16.44 4.889E+l0 3.060E+l0 4. l08E+l0 17.00 4.837E+l0 3.034E+l0 4.067E+l0 17.56 4.834E+l0 3.030E+l0 4.064E+l0 18.25 4.727E+l0 . 2.976E+l0 3.979E+l0 18.89 4.596E+l0 2.907E+l0 3.875E+ 10 19.32 4.366E+l0 2.782E+l0 3.689E+l0 19.43 4.281E+l0 2.736E+l0 3.621E+l0 19.67 4.139E+l0 2.659E+l0 3.507E+IO 20.01 4.020E+l0 2.604E+l0 3.415E+l0 4-8
Table 4-4 (Continued)
Azimuthal Variation of Fast Neutron Flux (E > 1.0 MeV)
At the Reactor Vessel Clad-Base Metal Interface Angle (deg} Cycle 8 Cycle 9 Ci'.cle 8-9 Avg.
20.35 3.947E+l0 2.580E+l0 3.363E+l0 20.59 3.950E+l0 2.599E+l0 3.373E+ 10 20.70 3.955E+l0 2.612E+l0 3.382E+IO 21.08 4.0llE+lO 2.661E+l0 3.435E+ 10 21.70 3.931E+l0 2.643E+l0 3.38 lE+IO 22.25 3.813E+l0 2.600E+l0 3.295E+IO 22.75 3.688E+l0 2.551E+l0 3.202E+ 10 23.25 3.557E+l0 2.499E+l0 3.105E+IO 23.75 3.426E+l0 2.448E+l0 3.008E+ 10 24.50 3.239E+l0 2.374E+l0 2.870E+!O
25.50 26.50 27.50 28.50 3.034E+l0 2.850E+l0 2.682E+l0 2.531E+l0 2.294E+l0 2.221E+l0 2.154E+l0 2.092E+l0 2.718E+l0 2.58IE+10 2.457E+IO 2.344E+l0 29.44 2.406E+l0 2.035E+l0 2.248E+l0 30.00 2.343E+l0 2.000E+lO 2.197E+l0 30.56 2.269E+l0 l.965E+l0 2.139E+l0 31.50 2.170E+10 l.908E+l0 2.058E+10 32.44 2.087E+l0 l.846E+10 l.984E+l0 33.00 2.048E+10 l.801E+10 1.942E+10 33.56 l.999E+10 1.762E+ 10 1.898E+l0 34.50 l.944E+10 l.692E+10 l.836E+ 10 35.50 l.904E+10 l.612E+10 l.780E+l0 36.25 1.886E+10 l.552E+ 10 l.744E+l0 36.75 1.873E+l0 1.51 lE+lO l.719E+l0
37.37 1.866E+10 l.463E+l0 l.694E+l0 4-9
Table 4-4 (Continued)
Azimuthal Variation of Fast Neutron Flux (E > 1.0_ MeV)
At the Reactor Vessel Clad-Base Metal Interface Angle {deg) Cycle 8 Cycle 9 Cycle 8-9 Avg.
38.12 l.858E+l0 l.409E+l0 l.667E+ IO 38.87 l.848E+l0 l.359E+l0 l.639E+l0 39.62 1.835E+l0 1.312E+l0 1.612E+l0 40.50 1.818E+l0 1.263E+l0 l.58 lE+lO 41.37 l.803E+l0 1.226E+l0 l.556E+l0 42.25 l.788E+l0 l.l 92E+l0 1.533E+ lO 43.12 1.780E+l0 l.l72E+l0 l.520E+ lO 43.88 1.774E+l0 l.l59E+l0 l.51lE+10 44.62 1.771E+ 10 l.152E+l0 l.506E+l0 Note: The reactor vessel clad/base metal interface is located at a radius of 219.075 cm.
Flux values given at this radius are interpolated. The units of flux are n/cm 2-sec.
4-10
Table 4-5 Summary of Fast Neutron Exposure Rates at the Reactor Vessel Clad/Base Metal Interface Fast Neutron Exposure Parameters Ratios Angle Flux (n/cm2-sec) {E > 0.1} dQa/sec
{deg} {E > 1.0} {E > 0.1} dQa/sec {E > 1.0} {E > l.02 Cycle 8 0 2.155E+l0 4.620E+l0 *3.253E-l l 2.14 l.5 lE-21 5 2.627E+l0 5.637E+l0 3.938E- l l 2.15 l.50E-2 t 10 3.883E+l0 8.227E+l0 5.746E-l l 2.12 . l.48E-2 l 15 4.84lE+lO l.022E+ l i 7.ll6E-ll 2.11 l.47E-2 I 20 4.020E+l0 9.l96E+l0 5.963E-l l 2.29 l.48E-2 I
-25 3.137E+l0 6.707E+l0 4.67lE-ll 2.14 l.49E-2 l 30 2.343E+l0 4.998E+l0 3.506E-l l 2.13 l.50E-2 l 35 l.924E+l0 4.133E+l0 2.88lE-ll 2.15 l.50E-2 l 40 l.827E+l0 3.856E+l0 2.739E-l l 2.11 l.50E-2 l 45 l.771E+l0 3.716E+l0 2.662E-l l 2.10 l.50E-2 l Cycle 9 0 2.082E+l0 4.391E+l0 3.124E-l 1 2.11 l.50E-2 l 5 2.245E+l0 4.747E+l0 3.361E-l l 2.11 l.50E-2 l 10 2.690E+l0 5.672E+l0 4.000E-11 2.11 l.49E-21 15 3.047E+10 6.42lE+lO 4.507E-l 1 2.11 l.48E-2 l 20 2.604E+l0 5.923E+l0 3.88lE-l l 2.27 l.49E-2 l 25 2.334E+l0 4.944E+l0 3.482E-l l 2.12 l.49E-2 l 30 2.000E+lO 4.223E+l0 2.984E-l l 2.11 l.49E-2 l 35 l.652E-tlO 3.510E+l0 2.462E- l l 2.12 l.49E-2 l 40 l.291E+l0 2.746E+l0 l.94lE-l l 2.13 l.50E-2 l 45 l.152E+l0 2.439E+l0 l.741E-ll 2.12 l.5 lE-21 4-11
Table 4-6 Relative Radial Distribution of Neutron Flux (E > 1.0 Me V)
Within the Reactor Vessel Wall for Cycle 8 Radius Vessel Azimuthal Angle
.lgn2.... Fraction 0 degrees 15 degrees 30 degrees 45 degrees 218.758 (a) 1.0204 l.0204 1.0203 1.0198 219.075 0.000 l.0000 1.0000 1.0000 1.0000 219.393 0.014 0.9796 0.9796 0.9797 0.9802 220.226 0.052 0.9066 0.9030 0.9056 0.9059 221.298 0.100 0.8071 0.7993 0.8049 0.8050 222.409 0.150 0.7080 0.6960 0.7042 \
0.7042 223.520 0.200 0.6169 0.6019 0.6121 0.6118 224.631 0.250 0.5350 0.5179 0.5294 0.5290 225.743 0.300 0.4624 0.4441 0.4564 0.4558
. 226.854 0.350 0.3986 0.3797 0.3923 0.3917
227.965 229.077 230.188 231.300 0.400 0.450 0.500 0.550 0.3429 0.2944 0.2524 0.2161 0.3239 0.2757 0.2343 0.1988 0.3365 0.2881 0.2462 0.2101 0.3359 0.2875 0.2456 0.2096 232.411 0.600 0.1847 0.1684 0.1791 0.1787 233.522 0.650 0.1577 0.1423 0.1524 0.1521 234.633 0.700 0.1345 0.1200 0.1294 0.1293 235.744 0.750 0.1145 0.1009 0.1097 0.1098 236.856 0.800 0.0972 0.0845 0.0928 0.0931 237.967 0.850 0.0824 0.0703 0.0782 0.0788 239.078 0.900 0.0695 0.0579 0.0655 0.0665 240.149 0.948 0.0585 0.0471 0.0547 0.0562 240.983 0.986 0.0507 0.0389 0.0469 0.0490 241.300 1.000 0.0475 0.0354 0.0438 0.0463 Note: Base Metal Inner Radius= 219.075 cm. Base Metal Outer Radius= 241.300 cm. Vessel Fraction is fraction of distance through the vessel base metal.
(a) Center of vessel clad.
4-12
Table 4-7 Relative Radial Distribution of Neutron Flux (E > 1.0 Me V)
Within the Reactor Vessel Wall for Cycle 9 Radius Vessel Azimuthal Angle (cm) Fraction 0 degrees 15 degrees 30 degrees 45 degrees 218.758 (a) 1.0208 1.0202 1.0205 l.O 195 219.075 0.000 l.0000 l.0000 1.0000 l.0000 219.393 0.014 0.9792 0.9798 0.9795 0.9805 220.226 0.052 0.9055 0.9039 0.905 l 0.9070 221.298 0.100 0.8048 0.8010 0.8036 0.8071 222.409 0.150 0.7046 0.6984 0.7023 0.7071 223.520 0.200 0.6126 0.6047 0.6096 0.6153 224.63 l 0.250 0.5301 0.521 l 0.5264 0.5329 225.743 0.300 0.4570 0.4474 0.453 l 0.4600
226.854 227.965 229.077 230.188 0.350 0.400 0.450 0.500 0.3930 0.3372 0.2887 0.2468 0.3830 0.3272 0.2789 0.2373 0.3889 0.3330 0.2847 0.2429 0.3960 0.3402 0.2917 0.2497 231.300 0.550 0.2106 0.2016 0.2069 0.2135 232.41 l 0.600 0.1795 0.1710 0.1760 0.1824 233.522 0.650 0.1528 0.1448 0.1495 0.1556 234.633 0.700 0.1297 0.1223 0.1267 0.1326 235.744 0.750 0.1099 0.1030 0.1072 0.1129 236.856 0.800 0.0929 0.0865 0.0903 0.0960 237.967 0.850 0.0782 0.0721 0.0759 0.0816 239.078 0.900 0.0653 0.0596 0.0632 0.0692 240.149 0.948 0.0543 0.0487 0.0525 0.0589 240.983 . 0.986 0.0463 0.0406 0.0446 0.0518 241.300 l.000 0.0428 0.0371 0.0413 0.0493 Note: Base Metal Inner Radius= 219.075 cm. Base Metal O~terRadius = 241.300 cm. Vessel Fraction is fraction of distance through the vessel base metal.
(a) Center of vessel clad.
4-13
Table 4-8 Relative Radial Distribution of Neutron Flux (E > 1.0 Me V)
Within the Reactor Vessel Wall Average for Cycles 8 and 9 Radius Vessel Azimuthal Angle
..i£ml.. Fraction 0 degrees 15 degrees 30 degrees 45 degrees 218.758 (a) 1.0206 1.0204 1.0204 1.0197 219.075 0.000 1.0000 1.0000 1.0000 l.0000 219.393 0.014 0.9794 0.9796 0.9796 0.9803 220.226 0.052 0.9061 0.9033 0.9054 0.9062 221.298 0.100 0.8062 0.7999 0.8044 0.8057 222.409 0.150 0.7066 0.6968 0.7035 0.7051 223.520 0.200 0.6151 0.6028 0.6111 0.6130 224.631 0.250 0.5329 0.5189 0.5282 0.5303 225.743 0.300 0.4602 0.4451 0.4551 0.4572 226.854 0.350 0.3963 0.3808 0.3910 0.3931 227.965 0.400 0.3405 0.3249 0.3351 0.3373 229.077 0.450 0.2920 0.2767 0.2867 0.2888 230.188 0.500 0.2501 0.2353 0.2449 0.2470 231.300 0.550 0.2138 0.1997 0.2089 0.2109 232.411 0.600 0.1826 0.1692 0.1779 0.1799 233.522 0.650 0.1557 0.1431 0.1513 0.1533 234.633 0.700 0.1325 0.1208 0.1284 0.1304 235.744 0.750 0.1126 0.1016 0.1087 0.1108 236.856* 0.800 0.0954 0.0851 0.0918 0.0940 237.967 0.850 0.0806 0.0709 0.0773 0.0797 239.078 0.900 0.0677 0.0585 0.0646 0.0673 240.149 0.948 0.0568 0.0476 0.0538 0.0571 240.983 0.986 0.0488 0.0394 0.0460 0.0499 241.300 1.000 0.0456 0.0360 0.0428 0.0473 Note: Base Metal Inner Radius= 219.075 cm. Base Metal Outer Radius= 241.300 cm. Vessel
Fraction is fraction of distance through the vessel base metal.
(a) Center of vessel clad.
4-:14
Table 4-9 Relative Radial Distribution of Neutron Flux (E > O. l Me V)
Within the Reactor Vessel Wall for Cycle 8 Radius Vessel Azimuthal Angle (cm) Fraction 0 degrees 15 degrees 30 degrees 45 degrees 218.758 (a) 0.9880 0.9926 0.9896 0.9893 219.075 0.000 l.0000 1.0000 l.0000 1.0000 219.393 0.014 l.O 120 1.0074 l.O 104 1.0107 220.226 0.052 l.0108 0.9939 l.0049 1.0050 221.298 0.100 0.9909 0.9602 0.9804 0.9803 222.409 0.150 0.9595 0.9151 0.9440 0.9438 223.520 0.200 0.9219 0.8656 0.9024 0.9019 224.631 0.250 0.8807 0.8145 0.8574 0.8572 225.743 0.300 0.8375 0.7629 0.8114 0.8112
226.8_54 227.965 229.077 230.188 0.350 0.400 0.450 0.500 0.7932 0.7484 0.7037 0.6592 0.7120
. 0.6620 0.6133 0.5661 0.7646 0.7181 0.6720 0.6265 0.7649 0.7189 0.6736 0.6292 231.300 0.550 0.6151 0.5203 0:5821 0.5858 232.411 0.600 0.5717 0.4761 0.5385 0.5437 233.522 0.650 0.5290 0.4334 0.4960 0.5027 234.633 0.700 0.4870 . 0.3920 0.4544 0.4629 235.744 0.750 0.4458 0.3518 0.4139 0.4243 236.856 0.800 0.4053 0.3127 0.3742 0.3869 237.967 0.850 0.3655 0.2745 0.3354 0.3505 239.078 0.900 0.3260 0.2368 0.2971 0.315 l 240.149 0.948 0.2877 0.1996 0.260 l 0.2816 240.983 0.986 0.2562 0.1682 0.2302 0.2555 241.300 1.000 0.2424 0.1542 0.2173 0.2450 Note: Base Metal Inner Radius= 219.075 cm. Base Metal Outer Radius= 241.300 cm. Vessel Fraction is fraction of distance through the vessel base metal.
(a) Center of vessel clad.
4-15
4-16 Table 4-l 1 Relative Radial Distribution of Neutron Flux (E > 0.1 Me V)
Within the Reactor Vessel Wall Average for Cycles 8 and 9 Radius Vessel Azimuthal Angle Jf!& Fraction 0 degrees 15 degrees 30 degrees 45 degrees 218.758 (a) 0.9888 0.9924 0.9900 0.9889 219.075 0.000 1.0000 1.0000 1.0000 1.0000 219.393 0.014 1.0112 1.0076 1.0100 LO 111 220.226 0.052 1.0084 0.9948 1.0036 1.0064 221.298 0.100 0.9863 0.9617 0.9779 0.9829 222.409 0.150 0.9528 0.9173 0.9404 0.9474 223.520 0.200 0.9134 0.8684 0.8978 0.9064 224.631 0.250 0.8706 0.8176 0.8520 0.8624 225.743 0.300 0.8261 0.7665 0.8053 0.8171 226.854 0.350 0.7807 0.7158 0.7580 0.7713
227.965 229.077 230.188 231.300 0.400 0.450 0.500 0.550 0.7351 0.6896 0.6446 0.6002 0.6660 0.6175 0.5703 0.5246 0.7110 0.6645 0.6189 0.5743 0.7257 0.6807 0.6365 0.5933 232.411 0.600 0.5566 0.4804 0.5306 0.5511 233.522 0.650 0.5137 0.4376 0.4881 0.5101 234.633 0.700 0.4718 0.3962 0.4466 0.4703 235.744 0.750 0.4306 0.3559 0.4062 0.4316 236.856 0.800 0.3903 0.3168 0.3667 0.3940 237.967 0.850 0.3506 0.2785 0.3280 0.3575 239.078 0.900 0.3113 0.2406 0.2899 0.3220 240.149 0.948 0.2731 0.2033 0.2530 0.2883 240.983 0.986 0.2415 0.1718 0.2231 0.2622 241.300 1.000 0.2275 0.1579 0.2100 0.2518 Note: Base Metal Inner Radius= 219.075 cm. Base Metal Outer Radius= 241.300 cm. Vessel Fraction is fraction of distance through the vessel base metal .
(a) Center of vessel clad.
4-17
l I
Table 4-12 Relative Radial Distribution of Iron Atom Displacement Rate (dpa/sj Within the Reactor Vessel Wall for Cycle 8 Radius Vessel Azimuthal Angle J9& Fraction 0 degrees 15 degrees 30 degrees 45 degrees 218.758 (a) 1.0160 1.0169 1.0162 1.0163 219.075 0.000 1.0000 1.0000 1.0000 1.0000 219.393 0.014 0.9840 0.9831 0.9838 0.9837 220.226 0.052 0.9245 0.9187 0.9226 0.9215 221.298 0.100 0.8432 0.8314 0.8394 0.8373 222.409 0.150 0.7620 0.7438 0.7559 0.7530 223.520 0.200 0.6865 0.6632 0.6788 0.6751 224.631 0.250 0.6179 0.5903* 0.6085 0.6046 225.743 0.300 0.5559 0.5250 0.5453 0.5412 226.854 0.350 0.5002 0.4667 0.4886 0.4845 227.965 0.400 0.4501 0.4147 0.4379 0.4339 229~077 0.450 0.4051 0.3685 0.3924 0.3887 230.188 0.500 0.3645 0.3272 0.3516 0.3484 231.300 0.550 0.3279 0.2903 0.3149 0.3122 232.411 0.600 0.2948 0.2572 0.2818 0.2797 233.522 0.650 0.2646 0.2274 0.2518 0.2505 234.633 0.700 0.2370 0.2004 0.2245 0.2240 235.744 0.750 0.2117 0.1757 0.1995 0.2000 236.856 0.800 0.1883 0.1530 0.1765 0.1780 237.967 0.850 0.1666 0.1320 0.1551 0.1578 239.078 0.900 0.1462 0.1123 0.1351 0.1392 240.149 0.948 0.1273 0.0936 0.1167 0.1224 240.983 . 0.986 0.1124 0.0784 0.1023 0.1098 241.300 1.000 0.1061 0.0718 0.0962 0.1048 Note: Base Metal Inner Radius= 219.075 cm. Base Metal Outer Radius= 241.300 cm. Vessel Fraction is fraction of distance through the vessel base metal .
(a) Center of vessel clad.
4-18
Table 4-13 Relative Radial Distribution of Iron Atom D_isplacement Rate (dpa/s)
Within the Reactor Vessel Wall for Cycle 9 *.
Radius Vessel Azimuthal Angle J9& Fraction 0 degrees 15'degr~es 30 degrees 45 degrees 218.758 (a) 1.0169 1.0168 1.0168 1.0157 219.075 0.000 1.0000 1.0000 1.0000 1.0000 219.393 0.014 0.9831
0.9832 0.9832 0.9843 220.226 0.052 0.9216 0.9194 0.9210 0.9235 221.298 0.100 0.8378 0.8329 0.8363 Q.8409 222.409 0.150 0.7541 0.7462 0.7512 0.7581 223.520 0.200 0.6766 0.6662 0.6728 . 0.6815 224.631 0.250 0.6062 0.5938 0.6015 0.6120 225.743 0.300 0.5429 0.5289 0.5375 0.5494 226.854 - 0.350. 0.4861 0.4709 0.4802 0.4933 227.965 0.400 0.4352 0.4192 0.4291 0.4431 229.077 0.450 0.3896 0.3731 0.3833 0.3982 230.188 0.500 0.3488 0.3319 0.3424 0.3580 231.300 0.550 0.3120 0.2950 0.3057 0.3218 232.411 0.600 0.2789 0.2619 0.2726 0.2893 233.522 0.650 0.2488 0.2320 0.2428 0.2599 234.633 0.700 0.2214 0.2049 . 0.2157 0.2333 235.744 0.750 0.1964 0.1801 0.1909 0.2090 236.856 0.800 0.1733 0.1574 0.1681 0.1868 237.967 0.850 0.1518 0.1363 0.1471 0.1664 239.078 0.900 0.1317 0.1164 0.1273 0.1475 240.149 0.948 0.1129 0.0977 0.1090 0.1305 240.983 0.986 0.0979 0.0826 0.0946 0.1180 241.300 1.000 0.0913 0.0760 0.0884 0.1132 Nore: Base Metal Inne_r Radius = 219.075 cm. Base Metal Outer Radius = 241.300 cm. Vessel Fraction is fraction of distance through the vessel base metal.
(a) Center of vessel clad.
4-19
4-20 Section 5 Evaluation of Cycle 9 In-Vessel Dosimetry Capsule This section presents the results qf the dosimetry analysis of the replacement in-vessel dosimetry capsule irradiated at the W-290 surveillance capsule location during Cycle 9. Results from the analysis of the w~290 surveillance capsule irradiated during Fuel Cycles 1-5 are also included here for comparison.
5-1. Measured Reaction Rates Following the Cycle 9 irradiation the in-vessel dosimetry capsule was removed from the W-290 loc,ation in the reactor. This capsule is described in Section 2. The remote disassembly of the dosimetry capsule was performed in one of the hot cells at the Westinghouse Science and Technology Center. During disassembly, the compartinent numbers and the contents of the flux monitor assemblies were checked against the data sheets .in Reference 11. No discrepancies were found. The individual dosimeters were packaged by compartment ID and were shipped to our counting facilities at Waltz Mill. At Waltz Mill the dosimetry was examined again and each individual dosimeter ID was verified prior to its being removed from the stainless steel sheath.
All cadmium and vanadium tubing was removed prior to weighing and counting. Nothing unusual was found during -the physical examination of the dosimeters.
The irradiation history of the Palisades Plant during Cycle 9 is listed in Appendix A. The _
irradiation history was obtained from Reference 32. Based on this reactor operating history, the individual sensor characteristics, and the measured specific activities given in Appendix A, cycle average* reaction rates referenced to a core power level of 2530 MWt were computed for each individual sensor.
The c_omputed reaction rates for the three sets of sensors irradiated in the in-vessel dosimetry capsule during *cycle- 9 are provided in Table 5-1.
238 237 The U * (n,f) and Np (n,f) reaction rates were obtained by averaging the results of the 238 measurement of three different fission products. In addition, ttie U fission rate measurements include analytical corrections for 235 U _impurities. Corrections for photofission reactions in the fission monitors were not calculated, but these are estimated to be less than one percent for the 5-1
237 238 Np monitors and less thari five percent for the U monitors. Omitting this correction gives a slightly conservative result for the fluence.
The corresponding foil data from Table 5-1 are also entered into Tables 5-2 t~rough 5-4 as appropriate. Note that the foil data for Set lAlF in Table 5-2 have been adjusted to the center of the capsule as noted below.
5-2. Results of the Least Squares Adjustment Procedure The results of the FERRET least squares analysis of each of the three sets of capsule dosimetry
are presented in Tables 5-2 through 5-4. In these tables, the derived exposure experienced at each sensor set l_ocation along with data illustrating the fit of both the calculated (a priori) and adjusted spectra to the measurements are given. Also included in the tabulations are the one sigma uncertainties associated with each of the derived exposure rates. The calculated spectrum was not renormalized for input to these calculations and thus rt?presents the calculated flux level*
at the maximum axial flux point.
The reaction rates input to these calculations are taken directly from Table 5-1 for the middle
( 1A4F) and bottom (1A7F) sets since the fuel cycle calculations indicate that the power gradient at these axial positions is small. For these two sets, the measured reaction rates are almost equal and the fuel cycle calculation averaged over the outer assemblies indicates that these locations are within three percent of the maximum axial position. For the top (lAlF) set, axial.gradient corrections were made to correct the reaction rates to the center of the capsule (+45 inches).
These corrections amounted to an increase of about four percent for the top location and a decrease of three percent for the bottom locatio_n within the capsule'. Since the calculated spectra that were input to FERRET were not normalized for axial location it is seen from Table 5-2 that the top set flux is about 11 percent lower than at the other two locations. This is consistent with the average outer assembly axial power shape which predicts the ratio of the power at the top location to the peak axial power location to be 0.86. This calculated ratio is only approximate since the outer assemblies vary in importance to the flux at this azimuthal location and they vary in axialshape near the top and bottom of the core. An R-Z DOT calculation, together with an R-8 adjoint DOT calculation, is necessary to accurately calcula_te the capsule axial flux profile.
Another FERRET analysis was also performed which used the average of the midplane and bottom sets. The FERRET results are given in Table 5-5. These two sets had almost equal .
responses which were taken to be equivalent to the maximum axial point. As can be seen from 5-2
a comparison of Tables 5-3 ~nd 5-4 with Table 5-5, the results for the individuarsets are almost identical with th~ average.
The previous results [ 15] for the updated analysis of the dosimetry in surveillance capsule W-290 are reproduced in Table 5-6. This analysis is very similar to the analysis of the Cycle 9 dosimetry, except that the earlier S8 DOT calculation for the average over Cycles 1-5 was used as input to FERRET. This difference does not have any appreciable impact on the result.
Comparison of the Cycle 1-5 results with the Cycle 9 result indicates that the results are very similar regarding the agreement of the measured data and calculations.
In Tables 5-2 through 5-:-5, *tlie columns labeled "c~lculated" represent the absolute values from the transport
. calculation for the surveillance capsule center location at a first octant equivalent angle of 20 degrees. The calculation in each case was normalized to the maximum flux axial position. The detailed a priori calculated and adjusted (derived by the least-squares procedure) flux-spectra for the average capsule calculation are given in Appendix B.
5-3
Table 5-1 Summary of Reaction Rates Derived from Multiple Foil Sensor Sets in the W-290 In-Vessel Dosimetry Capsule Irradiated During Cycle 9 Reaction Rate (rps/nucleus)
Set Set Set Set Set Set Reaction lAlF-U lAlF-L 1A4F-U 1A4F-L 1A7F-U 1A7F-L 46Ti(n,pi*l 8.88E-16 9.85E-16 9.58E-16 54Fe(n,pla) 3.95E-15 4.5 lE-15 4.37E-15 2JsU(n,t)<al l.67E-14 l.65E-14 l.73E-14 59Co(n;y)Cal l.74E-12 l.69E-12 l.67E-12 63 Cu(n,a) 5.45E-17 5.89E-17 5.8 lE-17 58 Ni(n,p) 5.65E-15 5.7 lE-15 5.92E-15 23sU(n,t)Cbl l.52E-14 l.80E-14 l.76E-14 231Np(n,t)Cbl 6.67E-14 6.69E-14 6.96E-14 59 Co(n;y) 2.37E-13 2.41E-13 2.37E-13 a) Bare dosimeter, all others were cadmium shielded.
b) Average of reaction rates determined by measurement of 103 Ru, 95 Zr, and 137 Cs fission products .
5-4
Table 5-2 Palisades Cycle 9 In-Vessel Dosimetry Top Capsule (1A1 F) Results
. Comparison of Calculated and Measured Integral Quantities Uncertainty in Ratio Measured Parameter Calculated Measured Cale/Meas Value (1 cr)
Flux (E > .1.0 Me V) 3.80E+IO 3.17E+IO 1.20 7%
(n/cm 2-s)
Flux (E > 0.1 MeV) 7.02E+IO 5.98E+IO 1.17 13%
(n/cm2-s)
Displacements per Atom per second 5.51E-ll 4.60E-l l 1.20 7%
(dpa/s)
Thermal Flux (E < 0.414 eV) 3.63E+IO 6.18E+IO 0.59 16%
(n/cm 2-s)
Total Flux l.67E+l 1 l.70E+l l 0.98 11 %
(n/cni2-s)
Comparison of Measured and Calculated Reaction Rates Reaction Rate (rps/nucleus) Ratio Cale/Meas Reaction Measured Calculated Adjusted Calculated Adjusted 63 Cu (n,a) 6°Co 5.28E-17 7.47E-17 5.40E-l 7 1.42. 1.02 54 Fe (n,p) 54Mn 4.lOE-15 5.30E-15 4.17E-15 1.29 1.02 58 Ni (n,p) 58Co 5.47E-15. 6.81E-15 5.43E-15 1.24 0.99 238 U (n,t) (Cd) l.47E-14 l.7 lE-14 l.41E-14 1.16 0.96 4
6Ti (n,p) 46 Sc *
1.15. -
9.23E-16 1.06E-15 8.68E-16 0.94 231Np (n,t) 6.46E-14 7.89E-14 6.55E-14 1.22 1.01 59 60 Co (n;y) Co l.8 lE-12 l.20E-12 l.79E-12 0.67 0.99 59 Co (n,y) 6°Co (Cd) 2.29E-13 3.32E-13 2.32E-13 1.45 1.01 Average Ratio Calculated/Measured for Threshold Reactions 1.25 . 0.99 5-5
Table 5-3 Palisades Cycle 9 In-Vessel Dosimetry Middle Capsule (IA4F) Results Comparison of Calculated and Measured Integral Quantities Uncertainty in
- Ratio Measured Parameter Calculated Measured Cale/Meas Value .(lcr)
Flux (E > l.0 Me V) 3.80E+10 3.52E+10 l.08 7%
(n/cm 2-s)
Flux (E > 0.1 MeV) 7.02E+10 6.53E+l0 l.08 13%
(n/cm 2-s)
Displacements per Atom per second 5.51E-ll 5.06E-l l l.09 7%
(dpa/s)
Thermal Flux (E < 0.414 eV) 3.63E+10 5.73E+10 0.63 16%
(n/cm 2-s)
Total Flux l.67E+l l l.74E+l l 0.96 11 %
(n/cm 2-s)
Comparison of Measured and Calculated Reaction Rates Reaction Rate (rps/nucleus) Ratio Cale/Meas Reaction Measured Calculated Adjusted Calculated Adjusted 63 Cu (n,a) 6°Co 5.89E-17 7.47E-17 5.98E-17 l.27 l.02 54Fe (n,p) 54 Mn 4.51E-15 5.30E-15 4.59E-15 l.17 l.02 58 Ni (n,p) 58Co 5.71E-15 6.81E-15 5.88E-15 l.19 l.03 238 U (n,f) (Cd) . l.80E-14 ' l.71E-14 l.58E-14 0.95 0.88 4"'ri (n,p) 46 Sc 9.85E-16 l.06E-15 9.39E-16 l.08 0.95 231Np (n,f) 6.69E-14 7.89E-14 7.02E-14 1.18 l.05 59 Co (n,y) 6°Co l.69E-12 l.20E-12 l.68E-12 0.71 0.99 59 60 l.01 Co (n;y) Co (Cd) 2.41E-l3 3.32E-l3 2.44E-13 l.38 Average Ratio Calculated/Measured for Threshold Reactions .l.14 0.99 5-6
Table 5-4 Palisades Cycle 9 In-Vessel Dosimetry Bottom Capsule (l A7F) Results Comparison of Calculated and Measured Integral Quantities Uncertainty in Ratio Measured Parameter Calculated Measured Cale/Meas Value (lcr)
Flux (E > 1.0 MeV) 3.80E+l0 3.52E+l0 1.08 7%
(n/cm 2-s)
Flux (E > 0.1 MeV) 7,02E+l0 6.62E+l0 1.06 13%
(n/cm 2-s)
Displacements per Atom per second 5.51E-ll 5.07E-l l 1.09 7%
(dpa/s)
Thermal Flux (E < 0.414 eV) 3.63E+l0 5.67E+l0 0.64 16%
(n/cm 2-s)
Total Flux l.61E+l l l.74E+l l 0.96 11%
(n/cm2-s)
Comparison of Measured and Calculated Reaction Rates Reaction Rate (rps/nucleus) Ratio Cale/Meas Reaction Measured Calculated Adjusted Calculated Adjusted 63 Cu (n,a) 6°Co . 5.81E-17 7.47E-17 5.89E-17 1.29 1.01 54Fe (n,p) 54 Mn 4.37E-15 5.30E-15 4.5.0E-15 1.21 ' 1.03 58 Ni (n,p) 58Co 5.92E-15 6.81E-15 5.90E-15 1.15 1.00 238 U (n,t) (Cd) l.76E-14 l.7 lE-14 l.57E-14 0.97 o~s9 4
~i (n,p) 46Sc 9.58E-16 l.06E-15 9.18E-16 1.11 0.96 237Np (n,t) 6.96E-14 7.89E-14 7.17E-14 1.13 1.03 59 Co (n,y) 60 Co l.67E-12 l.20E-12 l.66E-12 0.72 0.99 59 Co (n,y) 60 Co (Cd) 2.37E-13 3.32E-13 2.40E-13 1.40 1.01 Average Ratio Calculated/Measured for Threshold Reactions 1.14 0.99 5-7
Table 5-5 Palisades Cycle 9 In-Vessel Dosimetry Capsule (20 Degree Midplane) Average Results Comparison of Calculated and Measured Integral Quantities
Uncertainty in Ratio Measured Parameter Calculated Measured Cale/Meas Value (lcr)
Flux (E > to MeV) 3.80E+l0 3.52E+l0 1.08 7%
(n/cm 2-s)
Flux (E > 0.1 MeV) 7.02E+l0 6.58E+l0 l.07 13%
(n/cm 2-s)
Displacements per Atom per second 5.51E-ll 5.06E-l l 1.09 7%
(dpa/s)
Thennal Flux (E < 0.414 eV) 3.63E+l0 5.70E+l0 0.64 16%
(n/cm 2-s)
Total Flux l.67E+l l l.74E+ll 0.96 11%
(n/cm2-s)
Comparison of Measured and Calculated Reaction Rates Reaction Rate (rps/nucleus) Ratio Cale/Meas Reaction Measured Calculated Adjusted Calculated
Adjusted 63 Cu (n,a) 6°Co 5.85E-17 7.47E-17 5.94E-17 *1.28 1.01 54Fe (n,p) 54 Mn 4.44E-15 5.30E-15 4.55E-15 1.19 1.02 58 Ni (n,p) 58Co 5.82E-15 6.8 lE-15 5.89E-15 1.17 1.01 238 U (n,f) (Cd) l.78E-14 1.7 lE-14 l.57E-14 0.96 0.88 46Ti (n,p) 46 Sc 9.72E-16 l.06E-15 9.29E-16 1.10 0.96 231Np (n,f) 6.83E-14 7.89E-14 7.lOE-14 1.16 l.04
59 Co (n;y) 6°Co 59 Co (n;y) 6°Co (Cd) l.68E-12 2.39E-13 l.20E-12 3.32E-13 Average .Ratio Calculated/Measured for Threshold Reactions l.67E-12 2.42E-13 0.72 1.39 1.14 0.99 l.01 0.99 5-8
Table 5-6 Palisades Cycles 1-5 W-290 Surveillance Capsule (20 Degree Midplane) Average Results Comparison of Calculated and Measured Integral Quantities _
Uncertainty in Ratio Measured Parameter Calculated Measured . Cale/Meas Value (lcr)
Flux (E > 1.0 Me V) 7.35E+l0 6.71E+l0 1.10 9%
(n/cm2 -s)
Flux (E > 0.1 MeV) l.38E+l l l.29E+l l 1.06 16%
(n/cm 2-s)
Displacements per Atom per second 1.06E-10 9.66E-l l 1.10 .9%.
(dpa/s)
Thermal Flux (E < 0.414 eV) 7.21E+l0 6.76E+10 1.07 86%
(n/cm2 -s)
Total Flux 3.30E+l l 3.lOE+l l 1.06 27%
(n/cm2-s)
Comparison of Measured and Calculated Reaction Rates Reaction Rate (rps/nucleus) Ratio Cale/Meas Reaction Measured Calculated Adjusted Calculated Adjusted 63 Cu (n,a) 6°Co 1.04E-16 l.24E-16 l.05E-16 1.19 1.00 54 Fe (n,p) 54Mn 8.49E-15 9.78E-15 8.5 lE-15 l.15 1.00 58 58 Ni (n,p) Co 1.04E-14 l.26E-14 l.08E-14 1.21 1.04 238~ (n,f) (Cd) 3.09E-14 3.25E-14 2.93E-14 l.05 0.95 4 46 6Ti (n,p) Sc l.62E-15 l.85E-15 l.60E-15 l.14 0.99 Average Ratio Calculated/Measured for Threshold Reactions 1.15 1.00 5-9
Section 6 Evaluations of Reactor Cavity Dosimetry This section presents the results of the evaluations of the neutron sensor sets and gradient chains irradiated in the Palisades reactor cavity during Cycles 8 and 9. The evaluation of each set of data was accqmplished using a consistent approach based on the methodology discussed in Section 3, resulting in an accurate data base for defining the fast neutron exposure of the reactor vessel wall.
6-1. Cycle 8 Measured Reaction Rates Following the Cycle 8 irradiation, four multiple foil sensor sets and ten stainless steel gradient chains were removed from the reactor cavity as described in Section 2. The capsule identifications associated with each of the multiple foil sensor sets are listed in Table 6-1. The contents of each of these irradiation capsules is specified in Reference 1 and, for completeness, is also included in Appendix A to this report.
The shipment of irradiation capsules and gradient chains was examined upon receipt at our counting facilities at Waltz Mill. All dosimetry was found to be in good order. As the individual capsules were opened to remove the sensors, the sensor IDs were cross checked against the as-built documentation [l]. All IDs were in agreement with no discrepancies.
The physical examination of the individual sensors disclosed several unusual features. First, due to the relatively high temperatures in the reactor cavity and the sump during operation at Palisades the copper foils exhibited some discoloration. This discoloration was most pronounced for capsule E which is located axially below the insulation panels. Jn capsule E there was also some slight discoloration of the other metal foils as well. The second unusual observation, again attributed to the high temperatures, was that all eight of the natural uranium foils (both Westinghouse and N1ST PUDs) were totally oxidized to powder and that this oxidation process had split the aluminum foil covers. A small amount of oxide powder was observed inside the cadmium covers. During handling of one of the split packages of uranium oxide (Foil AE in
Capsule E), the contents were spilled. This dosimeter was deemed unrecoverable. All of the dosimetry was carefully cleaned following disassembly and again prior to counting. The depleted uranium foils (Westinghouse PUDs) were unaffected.
6-1
Note that in recognition of the problem with oxidizing the natural uranium foils, Cycle 1() and all future cycles use quartz (Cycle 10) or vanadium (future cycles) encapsulated U0 2 dosimeters.
The irradiation history of the Palisades Plant during Cycle 8 is listed in Appendix A. The irradiation history was obtained from Reference 31. Based on this reactor operating history, the individual sensor characteristics, and the measured specific activities given in Appendix A, cycle average reaction rates referenced to a core power level of 2530 MWt were computed for each multiple foil sensor and gradient chain segment.
An examin'ation of the measured specific activities for the long gradient chain retrieved from the 260 degree location shows that this chain did not extend down along the reactor vessel. It appears to have become piled up on structure in the reactor cavity during installation. It appears that the long gradient chain retrieved from the 340 degree location was also displaced by structure in the reactor cavity during installation. The results from this gradient chain are anomalously low compared to the other results. Note that the long gradient chains irradiated at these same locations during Cycle 9 do not display the same anomaly.
The computed reaction rates for the multiple foil sensor sets irradiated during Cycle 8 are provided in Table 6-2. Corresponding reaction rate data from the ten_ stainless steel gradient chains are recorded in Tables 6-3 through 6:-5. Table 6-3 provides the data for the short gradient chains which were attached to the support bar. Table 6-4 provides the data for the long gradient chains which were supported from the reactor cavity seal drip pan. Table 6-5 includes the average and one standard deviation on the average of the three long gradient chains at symmetric 54 54 58 58 30 degree angles. The tables include data for the Fe (n,p) Mn, Ni (n,p) Co, and 59 Co (n;y) 6°Co reactions as well as the fractional elemental composition of each chain.
54 54 The Fe (n,p) Mn reaction rates listed in Table 6-2 are an average of the bare and cadmium 238 237 covered measurements for each capsule. The U (n,f) and Np (n,f) reaction rates were obtained by averaging the results of the measurement of three different fission products. In 238 235 237 addition, the U fission rate measurements include corrections for U impurities and the Np results include corrections for gamma ray self-absorption. Corrections for photofission reactions in the fission monitors were not calculated, but these are estimated to be less than one percent 237 238 for the Np monitors and less than five percent for the U monitors. Omitting this correction
gives a slightly conservative result for the fluence. The data listed for Capsule E were corrected to an effective capsule center axial location by accounting for the axial neutron flux gradient that exists using gradients measured for 54 Fe and 58 Ni (fast neutron reactions) and 59 epithermal neutron reactions). This resulted in corrections of -4.1 percent and -7.4 percent for Co (thermal and 6-2
the bare Co and Fe foils, respectively,_ and +7.4 percent corrections for the fission foils located in the bottom pos'ition. Foils located in the middle position were very close to the capsule center so only fractional percent corrections were necessary.
The corresponding foil data fromTable 6-2 are also entered into Table 6-:3 as appropriate.
During the Cycle 9 I Cycle 1.0 replacement a set of measurements were made [40] to determine the radial location of the center of the U-tubes on the dosimetry bar in the reactor cavity relative to the outside surface of the mirror insulation on the reactor vessel. The bar is skewed radially.
The 270 degree end of the bar is closer to the reactor vessel than the 330 degree end. Given the fixed geometry of the dosimetry support bar a set of "best fit" radial distances were calculated.
In order to compare the DOT -calculated azimuthal reaction rate distribution with the full set of measured data (iron and nickel foils, short gradient chains, and long gradient chains) it was first necessary to apply a scaling factor to the support bar mounted dosimetry which would place it at a radius of 108 inches relative to the reactor centerline. These scaling factors were the ratio of the DOT calculated reaction rate at a radius of 108 inches in the reactor cavity to the reaction*
rate at the measured dosimetry radius. These ratios are listed in Table 6-1 along with the measured radii.
The measured reaction rates are shown plotted in Figures 6:.1 through 6-16. Figures 6-1 and 6-2 54 54 58 58 show the core midplane Fe (n,p) Mn and Ni (n,p) Co foil reaction rates plotted as a function of azimuthal angle with the corresponding calculated reaction rate. The foil data and
-the short gradient chain data are shown at the bar shifted angles. In addition the foil data and the short gradient chain data have been scaled to a constant radius of 108 inches as discuss~d above. The figures also include the corresponding reaction rates from the long gradient chains.
Figures 6-3 and 6-4 also show an azimuthal comparison of the calculated reaction rate to the measurements. In these figures, however, the calculated reaction rate has been scaled down by the average difference between calculation and measurement in order to better illustrate the azimuthal shape agreement between calculations and measurements. It is clear from these two figures that the six degree azimuthal shift determined previously [ 14] for the support bar mounted dosimetry is highly consistent with the calculated azimuthal reaction rate distribution.
Figures 6-5 thfough 6-7 show the short gradient chain reaction rates plotted as a function of distance from the core midplane. Note that no radial adjustment factors have been applied to this data. Figures 6-8 through 6-16 show the long -gradient chain reaction rates plotted as a function distance from the core midplane. The solid lines are Bezier fits to the data drawn as an aid to visualization only.
6-3
6-2. Cycle 9 Measured Reaction Rates Following the Cycle 9 irradiation, seven multiple foil sensor sets and eleven stainless steel gradient chains were removed from the reactor cavity as described in Section 2. The capsule identifications associated with each of the multiple foil sensor sets are given in Table 6-6. The contents of each of these irradiation capsules is specified in References I and 2. For completeness the data is also included in Appendix A to this report.
The shipment of irradiation capsules and gradient ch(iins was examined upon receipt at our counting facilities at Waltz Mill. All dosimetry was found to be in good order. As the individual capsules. were opened to remove the sensors, the sensor IDs were cross checked against the as-built documentation [1,2]. ~capsule by capsule description of the contents of the irradiation capsules follows.
Capsule A (270 degrees - Core Midplane): All of the dosimetry IDs matched the data in*
Table 2-3 in WCAP-11911. All of the metal foils were bright and shiny with a couple of exceptions. As had been observed in the previous cycle, the 0.007" thick natural uranium foils (Reactor Experiments Catalog No. 503) had totally oxidized to powder. This was true for both the Westinghouse supplied foils and those in the NIST PUD sets. An interesting temperature-related observation was made. The inside of the cadmium cover had taken a full clear impression of the stamped "K" on the adjacent iron foil. This is the first time that this has been observed.
It is felt to be an indication that the temperatures were high enough for the cadmium to soften somewhat. The melting point for cadmium is 610 °P.
Capsule C (270 degrees - Bottom of Core): All of the dosimetry IDs matched the data in Table 2-3 in WCAP-11911. The foils in this set had discolorations that were indicative of high temperatures. In particular, the iron foils had a "blue-black" tempered look. Machinery's Handbook indicates temperatures on the order of 560 to 570 °P are required to achieve this coloration. In compartment C-1 (bare foils), the aluminum foil filler and the CoAl foil adhered to one another. This partial fusion was also indicative of high temperatures. The 0.007" thick natural uranium foils (Reactor Experiments Catalog No. 503) had also totally oxidized to powder.
This was true for both the Westinghouse supplied foils and those in the NIST PUD sets. The inside of this cadmium cover had also taken a full clear impression of the stamped "M" on the adjacent iron foil. Note that this capsule is below the insulation panels in a much higher temperature environment than Capsule A on the core midplane. The lower split ring on this 6-4
gradient chain was corroded and the lower length of the stainless steel bead chain exhibited discoloration consistent with high temperatures.
Capsule J (S-2 280 degrees - Core Midplane): All of the dosimetry IDs matched the data in Table 2-3 in WCAP-12847 except that the uranium foils were in Compartment J-3 not J-2. This is a typographical ~rror in the table. All of the metal foils were bright and shiny with the exception of the natural uranium foils. As had been observed in the previous cycle, the 0.007" thick natural uranium foils (Reactor Experiments Catalog No. 503) had totally oxidized to powder. The inside of the cadmium cover had not taken any impression of the adjacent iron foil.
The lower split ring on this gradient chain was also corroded.
Capsule K (S-2 290 degrees - Core Midplane): All of the dosimetry IDs matched the data in Table 2-3 in WCAP-12847 except that the uranium foils were in Compartment K-3 not K-2.
This is a _typographical error in the table. All *of the metal foils were bright and shiny with a couple of exceptions. The copper foil had some discoloration indicative of elevated temperature.
As had been observed in the previous cycle, the 0.007" thick natural uranium foils (Reactor*
Experiments Catalog No. 503) had totally oxidized to powder. The inside of the cadmium cover had not taken any impression of the adjacent iron foil.
Capsule L (S-2 290 degrees - Bottom of Core): All of the dosimetry IDs matched the data in Table 2-3 in WCAP-12847 except that the uranium foils were in Compartment L-3 not L-2. This is a typographical error in the table. The foils in this set had discolorations that were indicative of high temperatures. In particular, the iron foils had a "blue-black" tempered look. The copper foil was jet black, and the niobium foil was golden yellow. The 0.007" thick natural uranium foils (Reactor Experiments Catalog No. 503) had also totally oxidized to powder. Note that this capsule is below the insulation panels in a much higher temperature environment than the core midplane.
-Capsule F (300 degrees - Core Midplane): Note that this capsule spent Cycle 8 on the core midplane and due to a repositioning error during the Cycle 8/9 replacement spent Cycle 9 at approximately the bottom of the core. All of the dosimetry IDs matched the data in Table 2-3 in WCAP-11911. The foils in this set had discolorations that were indicative of high temperatures. In particular, the iron foils had a "blue-black" tempered look. The niobium foil
was bright blue in color. In compartment F-1 (bare foils), the aluminum foil filler, the CoAl foil, and the capsule lid adhered to one another. This partial fusion was also indicative of high temperatures. The 0.007" thick natural uranium foils (Reactor Experiments Catalog No. 503) had also totally oxidized to powder. This was true for both the Westinghouse supplied foils and those 6-5
in the NIST PUD sets. The inside of this cadmium cover had also taken a full clear impression of the stamped "P" on the adjacent iron foil. The lower length of the stainless steel bead chain exhibited discoloration consistent with high temperatures.
Capsule N (S-2 315 degrees - Core Midplane): All of the dosimetry IDs matched the data in Table 2-3 in WCAP-12847 except that the uranium foils were in Compartment N-3 not N-2.
This is a typographical error in the table. All of the metal foils were bright and shiny with the exception of the natural uranium foils. As had been observed in the previous cycle, the 0.007" thick natural uranium foils (Reactor Experiments Catalog No. 503) had totally oxidized to powder. The inside of the cadmium cover had not taken any impression of the adjacent iron foil.
The closure screws in this capsule were observed to be rusty.
Note that in recognition of the problem with oxidizing the natural uranium foils, Cycle 10 and all future cycles use quartz (Cycle 10) or vanadium (future cycles) encapsulated U0 2 dosimeters.
The impression of the iron foil ID in the cadmium cover was limited to those capsules which had*
been in for both Cycle 8 and 9. It was not observed in those capsules which were in for only Cycle 8 or only Cycle 9.
The irradiation history of the Palisades Plant during Cycles 8 and 9 is listed in Appendix A. The irradiation history was obtained from References 31 and 32. Based on this reactor operating history, the individual sensor characteristics, and the measured specific activities given in Appendix A, cycle average reaction rates referenced to a core power level of 2530 MWt were computed for _each multiple foil sensor and gradient chain segment.
. The computed reaction rates for the multiple foil sensor sets irradiated during Cycle 9 are provided in Table 6-7. Note that Capsules A and C were irradiated for both Cycle 8 and Cycle 9. Corresponding reaction rate data from the eleven stainless steel gradient chains are recorded in Tables 6-8 and 6-9. Table 6-8 provides the data for the short gradient chains which were attached to the support bar. Table 6-9 provides the data for the long gradient chains which were supported from the reactor cavity seal drip pan. The tables include data for the 54 59 Fe (n,p) 54 Mn, 58 Ni (n,p) 58 Co, and Co (n,y) 6°Co reactions as well as the fractional elemental composition of each chain.
The 54 Fe (n,p) 54 Mn reaction rates listed in Table 6-7 are an average of the bare an~ cadmium covered measure~ents for each capsule. The 238 U (n,f) and 237 Np (n,f) reaction rates were obtained by averaging the results of the measurement of three different fission products. In 6-6
1
addition, the 238 U fission rate measurements include' corrections for 235 corrections were made for fission product gamma ray self-absorption but these are estimated U impurities.
be less than two percent. Corrections for photofission reactions in the fission monitors were not calculated, but these are estimated to be less than one percent for the 237 Np monitors and less No to 238 than five percent for the U monitors. Omitting this correction gives a slightly conservative result for the fluence. The data listed for Capsule C and Capsule L were corrected to an effective capsule center axial location by accounting for the axial neutron flux gradient that exists using 54 58 59 gradients measured in Cycle 8 for Fe and Ni (fast neutron reactions) and Co (thermal and epithermal neutron reactions). This resulted in corrections of -4. l percent and -7.4 percent for the bare Co and Fe foils, respectively, and +7.4 percent corrections for the fission foils located in the bottom position. Foils located in the middle position were very close to the capsule center so only fractional percent corrections were necessary.
The corresponding foil data from Table 6-7 are also entered into Table 6-8 as appropriate.
During the Cycle 9 I Cycle 10 replacement a set of measurements were made [40] to determine the radial location of the center of the U-tubes on the dosimetry bar in the reactor cavity relative to the outside surface of the mirror insulation on the reactor vessel. The bar is skewed radially.
The 270 degree end of the bar is closer to the reactor vessel than the 330 degree end. Given the fixed geometry of the dosimetry support bar a set of "best fit" radial distances were calculated.
In order to compare the DOT calculated azimuthal reaction rate distribution with the full set of measured data (iron ahd nickel foils, short gradient chains, and long gradient chains) it was first necessary to apply a scaling factor to the support bar mounted dosimetry which would place it at a radius of 108 inches relative to the reactor centerline. These scaling factors were the ratio of the DOT calculated reaction rate at a radius of 108 inches in the reactor cavity to the reaction rate at the measured dosimetry radius. These ratios are listed in Table 6-6 along with the measured radii.
The measured reaction rates are shown plotted in Figures 6-17 through 6-34. Figures 6-17 and 54 54 58 58 6-18 show the core midplane Fe (n,p) Mn and Ni (n,p) Co foil reaction rates plotted as a function of azimuthal arigle with the corresponding calculated reaction rate. The foil data and the short gradient chain data are shown at the bar shifted angles. In addition the foil data and the short gradient chain data have been scaled to a constant radius of 108 inches as discussed
above. The figures also include the corresponding reaction rates from the long gradient chains.
Figures 6-19 and 6-20 also show an azimuthal comparison of the calculated reaction rate to the measurements. In these figures, however, the calculated reaction rate has been scaled down by the average difference between calculation and measurement. It is clear from these two figures 6-7
. that the six degree azimuth_al shift determined previously [14] for the support bar mounted dosimetry is highly consistent with the calculated azimuthal rnaetion rate distribution.
Figures 6-21 through 6-23 show the short gradient chain reaction rates plotted as a function of distance from the core midplane. Note that no radial adjustment factors have been applied to this data. Figures 6-24 through 6-34 show the long gradient chain reaction rates plotted as a function distance from the core midplane. The solid lines are Bezier fits to the data drawn as an aid to visualization only.
6-3. Results of the Least Squares Adjustment Procedure The results of the application of the least squares adjustment procedure t.o the four sets of
multiple foil measurements obtained from the Cycles 8 and 9 cavity irradiations are provided in Tables 6-11 through 6-20. In these tables, the derived exposure experienced at each sensor set location along with data illustrating the fit of both the calculated (a priori) and adjusted spectra*
to the measurements are given. Also included in the tabulations are the one sigma uncertainties qSSociated with each of the derived exposure rates.
The columns labeled "calculated" in Tables 6-11 through 6-20 represent the absolute values from the transport calculation for the cavity dosimetry location at that azimuthal angle (Table 4~ l for
. Cycle 8 and Table 4-2 for Cycle 9) and radial location. The analysis assumed an azimuthal dosimetry .location shifted by six degrees (as indicated by the results presented in Sections 6-1 and 6-2) and a radial location as measured for the dosimetry support bar relative to the vessel insulation. The evaluation for the three bottom capsules (located 66 inches below the core
, midplane) used a flux-spectrum renormalized by the ratio of the cadmium-shielded 54 F~ (n,p) reaction at the bottom to that at midplane. Thus, the comparisons presented for the dosimetry located at the bottom locations indicate only the degree to which the relative neutron energy spectra matched the measured data before and after adjustment and not a true C/M comparison.
The choice of normalization factor does -not have a significant impact on the unfolded result because of the-large uncertainty assigned to the a priori flux input, as long as the magnitude of the normalized flu'x is reasonably consistent with the measurements'.
Details of the adjusted cavity neutron spectra derived by the least-squares procedure are given in Appendix B.
6-8
To develop axial !J"averses of_fast neutron exposure rates in the reactor cavity, the results of the least squares adjustment of the multiple foil data must be combined with the measurements from the gradient chains. Although the gradient chain data at each angle can be used directly for this purpose, it was deemed appropriate to average the axial profile data: This averaging overcomes the difficulty that gradient data for the whole core height is not available at every angle and also the averaging minimizes statistical fluctuations in the data . .An examination of all the gradient data in this section indicates that the data demonstrates a consistent axial profile shape within statistical uncertainty. The 54 Fe (n,p) 54 Mn reaction rate gradient chain data were used to establish an average relative axial distribution over the measurement range and this distribution .
58 58 is presented in Table 6-21. The Ni (n,p) Co data were not used because this data is less reliable for evaluating the axial profile due to its short half-life and the resulting influences from changing core power distributions during the fuel cycle.
Since the short chains attached to the dosimetry support bar only cover half of the core. height, only the long chains were utilized in the average. Table 6-21 contains average axial profiles for both Cycle 8 and Cycle 9 and the standard deviation of the average at each height. The standard*
deviation of the shape within the core region averaged about three percent for both cycles. Out of the core region, the standard deviation increases due to neutron scattering caused by the steel .
support structure~ No consistent shape bias could be discerned between the two cycles and the standard deviation_s of the Cycle 8/Cycle 9 ratio for the in-core and total data are almost identical to that for the shape for each cycle alone. Therefore, an average over all the long chain axial data for both cycles was felt to be appropriate to minimize the data scatter and provide best
.estimate fluence values atoff-midplane locations. This average was obtained by normalizing the 54 54 Fe (n,p) Mn measurements from the long chains at each angle to the average peak value at that angle and then averaging these shapes to give the average axial profile. The average peak value at each angle is the average of measuremerits over a two-foot span about the apparent peak ..
This average was calculated to minimize the effect of random scatter in the data. The available angles for the long chain data do not cover all the dosimetry angles, but the chains are located near the most important angles corresponding to the vessel azimuthal peak flux and to the
longitudinal weld locations.
The resultant axial distributions of fast neutron flux (E > 1.0 Me V) and (E > 0.1 Me V), and the iron atom displacement rate (dpa/sec) are given in Section 8 based on. the average for the two cycles tabulated in last column in Table 6-21. Note that this column has been renormalized to give a peak relative flux of 1.0. The axial fast neutron flux shape is depicted graphically in Figure 6-35.
6-9
Table 6-1 Consumers Power Company Palisades Nuclear Plant Location of Cycle 8 Support Bar Mounted Dosimetry in the Reactor Cavity Reference First *Bar Azimuthal Octant Shifted Core. Midplane Core Bottom Location Equivalent Angle 270 deg 0 deg 6 deg None Removed 280 deg 10 deg 16 deg Capsule B 290 deg 20 deg 26 deg Capsule D Capsule E 300 deg 30 deg 36 deg None Removed 315 deg 45 deg 39 deg Capsule G 330 deg 30 deg 24 deg Gradient Chain Only Calculated Cycle 8 Reaction Rate Ratios Reference Bar Dosimeter (RR at R = 108" I RR at Dosimeter Radius)
Azimuthal Shifted Radius 54 54 58 58 Fe (n,p) Mn Ni (n,p) Co Location Angle (inches) 270 deg 6 deg 100.7 0.952 0.952 280 deg 16 deg 101.6 0.885 0.885 290 deg 26 deg 102.5 0.947 0.947 300 deg 36 deg 103.5 0.982 0.982 315 deg 39 deg 105.3 0.989 0.989 330 deg 24 deg 107.6 0.996 0.996 6-10
Table 6-2 Summary of Reaction Rates Derived from Multiple Foil Sensor Sets Irradiated During Cycle, 8 Reaction Rate (rps/nucleus)
Capsule Capsule Capsule Capsule Reaction B D E G 63 Cu (n,a) 9.76E-l9 7.51E-19 2.00E-19 5.53E-l 9 46Ti (n,p) l.45E-l 7 l.l lE-17 3.35E-18 7.89E-l8
. 54Fe (il,p) 7.42E-l7 5.60E-17 l.68E-l 7 4.00E-17 58 Ni (n,p) l.04E-16 7.81E-17 2.58E-17 5.51E-17 238 U (n,f) 4.14E-16 3.19E-16 l.09E-16 2.16E-l6 237Np (n,f) 6.72E-15 4.97E-15 l.86E-15 3.65E-15 59Co (n;y)Ca) 4.7 lE-14 4.41E-14 2.53E-14 4.90E-14 59 Co (n,y) 3.13E-14 3.04E-14 l.78E-14 2.95E-14 Capsule Identification Reference First Bar Azimuthal Octant Shifted Core Core Location Equivalent Angle Midplane Bottom 280 deg 10 deg 16 deg Capsule B 290 deg 20 deg 26 deg Capsule D Capsule E 3.15 deg 45 deg 39 deg Capsule G a) Bare foil, all others were cadmium shielded.
6-11
Table 6-3 Reaction Rates Derived From the Support Bar Mounted Stainless Steel Gradient Chains irradiated During Cycle 8 Reference Azimuth: 280 deg. First Octant Equivalent Angle: l 0 deg.
Bead Chain Tag ID: 280 Bar Shifted Angle: 16 deg.
Chain Composition Fe: 0.706 Ni: 0.0881 Co: 0.0018 Feet [<------------------ Reaction Rate ------------------>]
from Lab - Mn - Co - Co Midplane Sample#
+0.5 90-1915A 6.92E-l7 l.12E-l6 4.8 !E-14
0.0
-0.5
-l.0
- l.5 Bare Foils 90-19158 90-1915C 90-19150 7.42E-17 7.04E-l 7 7.05E-17 6.86E-17 l.04E-l6 l.17E-16
. l. lOE-16 l.05E-16 4.7 !E-14 4.8 lE-14 4.80E-14 4.73E-14
-2.0 90-1915E 6.59E-17 l.0 lE-16 4.59E-14
-2.5 90-1915F 5.57E-17 l.O lE-16 4.46E-l4
-3.0 90-19150 5.36E-17 8.73E-17 4.28E-14
-3.5 90-1915H 5. l lE-17 8.36E-17 4.12E-14
-4.0 90-19151 3.74E-17 6.98E-l 7 3.86E-14
-4.5 90-19151 3.09E-17 5.22E-17 3.28E-14
-5.0 90-1915K 2.08E-17 3.47E-17 2.80E-14
-5.5 90-1915L l.38E-17 2.49E-17 2.57E-14 6-12
Table 6-3 (Continued)
Reaction Rates Derived From the Support Bar Mounted Stainless Steel Gradient Chains irradiated During Cycle 8 Reference Azimuth: 290 deg. First Octant Equivalent Angle: 20 deg.
Bead Chain Tag ID: 290 Bar Shifted Angle: 26 deg.
Chain Composition Fe: 0.683 Ni: 0.092 Co: 0.0017 Feet [<------------------ Reaction Rate ------------------>]
from Lab - Mn - Co - Co Midplane Sample#
+0.5 90-l916A 5.24E-l7 8. l3E-l7 4.39E-l4
0.0
-0.5
-l.0
-l.5 Bare Foils 90-19168 90-l916C 90-19160 5.60E-l7 5.34E-17 5.44E-l7 5.34E-l7 7.SIE-17 7.88E-l7 7.92E-l7 8.2IE-l7 4.41E-l4 4.37E-14 4.39E- l4 4.33E-l4
-2.0 90-1916E 5.22E-l7 8.llE-17 4.30E-14
-2.5 90-l916F 4.91E-17 7.79E-l 7 4. l4E-l4
-3.0 90-19160 4.68E-17 7.20E-l7 4.lOE-14
-3.5 90-l916H - 4.55E-17 6.87E-17 3.94E-l4
-4.0 90-19161 3.85E-l7 6.44E-17 3.73E- l4
-4.5 90-19161 3.24E-l 7 5.00E-17 3.49E-l4
-5.0 90-l916K 2.l6E-l7 3.36E-l7 2.80E-l4
-5.5 Bare Foils l.68E- l 7 2.58E-l7 2.53E- l4 6-13
- Table 6-3 (Continued)
Reaction Rates Derived From the Support Bar Mounted Stainless Steel Gradient Chains Irradiated During Cycle 8 Reference Azimuth: 315 deg. First Octant Equivalent Angle: 45 deg.
Bead Chain Tag ID: 315 Bar Shifted Angle: 39 deg.
Chain Composition Fe: 0.673 Ni: 0.0868 Co: 0.0016 Feet [<------------------ Reaction Rate ------------------>]
from Lab - Mn - Co - Co Mid plane Sample#
+0.5 90-1918A 3.94E-17 6.30E-17 5.23E-14 0.0 Bare Foils 4.00E-17 5.5 lE-17 4.90E~ 14
-0.5 90-19188 3.86E-17 5.61E-17 5.28E-14
-1.0 90-1918C 3.86E-17 5.42E-17 5. l8E- l4
-l.5 90-19180 3.45E-l7 5.72E-17 5; 18E-14
-2.0 90-1918E 3.63E-17 5.60E-17 5.03E-l4
-2.5 90-1918F 3.20E-17 4.88E-17 4.89E-l4
-3.0 90-19180 3.14E-17 4.89E-17 4.57E-14
-3.5 90-1918H 2.80E-l7 4.45E-17 4.44E-14
-4.0 90-19181 2.44E-17 4.24E-17 4.06E- l4
-4.5 90-1918J . 2.24E-17 3.53E-l7 3.78E-14
-5.0 90-1918K l.59E-17 2.64E-l7 3.03E-14
-5.5 90-1918L l.18E-17 2.16E-17 2.57E- l4 6-14
Table 6-3 (Continued)
Reaction Rates Derived From the Support Bar Mounted Stainless Steel Gradient Chains Irradiated During Cycle 8 Re~erence Azimuth: 330 deg. First Octant Equivalent Angle: 30 deg.
Bead Chain Tag ID: 330 Bar Shifted Angle: 24 deg.
Chain Composition Fe: 0.687 Ni: 0.0935 Co: 0.0016 Feet [ <------------------ Reaction Rate __________ : _______ >]
from Lab - Mn - Co - Co Mid plane Sample#
+0.5 90-1919A 5.42E-17 8.36E-17 5.85E-14 0.0 90-19198 6.04E-17 7.95E-17 5.83E-14
-0.5 90-1919C 5.73E-l7 8.61E-l7 5.83E-14
-l.0 90-l9 l9D 5.8 lE-17 8. l9E-l7 5.69E-14
-l.5 90-l9 l9E 5. l3E-l 7 7.67E-l 7 5.58E-14
-2.0 90-l919F 4.89E-l7 7.88E-17 5.38E-14
-2.5 90-19190 4.57E-17 7.15E-17 5. llE-14
-3.0 90-l919H 4.16E-17 6.42E-17 4.81E-14
-3.5 90-19191 3.44E-l7 5.35E-l7 4.49E-14
-4.0 90-19191 2.95E-l 7 4.47E-l7 4. l2E-14
-4.5 90-l919K 2. lOE-17 2.98E-l7 3.31E-14
-5.0 90-1919L l.52E-l7 2.37E-l7 2.83E-14
-5.5 90-1919M 9.07E-l8 l.72E-17 2.60E-l4 6-15
Table 6-4
Reaction Rates Derived From the Long Stainless Steel Gradient Chains Irradiated During Cycle 8 Reference Azimuth: 30 deg. First Octant Equivalent Angle: 30 deg.
Bead Chain Tag ID: 30 Chain Composition Fe: 0.644 Ni: 0.0874 Co: 0.0013 Feet [<------------------ Reaction Rate ------------------> J from Lab - Mn - Co - Co Midplane Sample#
+8.0 90-l909A 2.87E-l8 5.70E-l8 2.03E-14
+7.5 90-19098 3.82E-l8 6.41E- l 8 2.21E-l4
+7.0 90-l909C 7.34E-18 l. l4E-17 2.61E-14
+6.5 90-19090 9. l 7E-18 l.42E-l7 2.7 lE-14
+6.0 90-l909E l.55E-17 2.32E-l7 3. lOE-14
+5.5 90-1909F l.95E- l 7 3.28E-l7 3.18E-14
+5.0 90-19090 2.53E-17 3.91E-17 3.67E-l4
+4.5 90-1909H 3.13E-17 4.95E-l 7 3.94E-14
+4.0 90-19091 3.35E-17 5.22E-17 3.90E-14
+3.5 90-19091 3.97E-17 6.0lE-17 4.35E-14
+3.0 90-1909K 4.18E-l7 6.2 lE-17 4.54E-14
+2.5 90-1909L 4.41E-17 6.23E-l7 4.65E-14
+2.0 90-1909M 4.37E-17 6.14E-17 4.9 lE-14
+1.5 90-1909N 4.29E-17 6.34E-17 5.06E-14
+1.0 90-19090 4.38E-17 6.64E-17 5.08E-14.
+0.5 90-1909P 4.50E-l7 6.41E-l 7 5.29E-14 0.0 90-1909Q 4.58E-17 6.63E-l7 5.35E-14
-0.5 90-l909R 4.55E-17 6.72E-17 5.30E- l4
-l.O 90-1909S 4.59E-17 6.74E-l 7 5.46E-14
-1.5 90-1909T 4.32E-17 7.30E-17 5.29E-14
-2.0 90-19090 4.61E-17 6.93E-17 5.32E-14
-2.5 90-1909V 4.41E-17 6.96E-17 5.22E-14
-3.0 90-1909W 4.21E-17 6.48E-17 4.94E-14
-3.5 90-1909X 4.03E-17 5.88E-17 4.79E-14
-4.0 90-1909Y 3.64E-17 5.47E-l7 4.47E-14
-4.5 90-1909Z 2.9lE-17 4.87E- l 7 3.99E-l4 6-16
Table 6-4 (Continued)
Reaction Rates Derived From the Long Stainless Steel
Gradient Chains Irradiated During Cycle 8 Reference Azimuth: 90 deg. First Octant Equivalent Angle: 0 deg.
Bead Chain Tag ID: 90 Chain Composition Fe: 0.677 Ni: 0.091 Co: 0.00 l 9 Feet [<--------------~--- Reaction Rate ------------------> l from Lab - Mn - Co - Co Midplane Sample#
+8.0 90-1910A 4.06E-18 6.80E-18 2.04E-14
+7.5 90-19108 5.27E-18. . 9.34E-18 2.24E-14
+7.0 90-1910C 8.8 lE-18 l.69E-l 7 2.67E-14
+6.5 90-19100 l.33E-l 7 2.17E-D 2.87E-14
+6.0 90-1910E l.97E-17 2.94E-17 3.21E-14
+5.5 90-1910F 2.47E-17
3.89E-17 3.42E-14
+5.0 90-19100 3.00E-17 4.73E-l 7 3.89E-14
+4.5 90-19 lOH 3.63E-17 5.50E-17 4. l 3E-14
+4.0 90-19101 3.99E-17 6.05E-17 4.33E-14
+3.5 90-19101 4.40E-17 7.14E-17 4.72E-14
+3.0 90-1910K 4.59E-17 7.37E-17 4.85E-14
+2.5 90-1910L 4.75E-17 7.40E-17 5.26E-14
+2.0 90-1910M 4.84E-17 8.03E-17 5.65E-14
+l.5 90-1910N 4.70E-17 7.15E-17 5.3 lE-14
+l.O 90-19100 4.52E-17 7.69E-l 7 5.85E-14
+0.5 90-1910P 4.77E-17 7.41E-17 5.77E-14 0.0 90-1910Q 5.33E-17 7.09E-17 5.95E-14
-0.5 90-1910R 5.03E-17 7.35E-17 6.0lE-14
- -LO_ 90-1910S _ 4.58E-17 7.20E-17
5.95E-14
-1.5 90-1910T 4.64E-17 6.70E-17 5.87E-14
-2.0 90-1910U 4.44E-17 6.80E-17 5.7 lE-14
-2.5 90-1910V 4.45E-17 7.16E-17 5.50E-14
-3;0 90-1910W 3.80E-17 6.39E-17 5.09E-14
.-3.5 90-1910X 4.20E-17 6.05E-17 4.92E-14
-4.0 90-1910Y 3.52E-17 5.05E-17 4.45E-14
-4.5 90-1910Z 2.89E-17 4.14E-17 4. UE-14 6-17
1 Table 6-4 (Continued)
Reaction Rates Derived From the Long Stainless Steel
. Gradient Chains Irradiated During Cycle 8
.Reference Azimuth: 150 deg. First Octant Equivalent Angle: 30 deg.
Bead Chain Tag ID: (NONE)
Chain Composition Fe: 0.667 Ni: 0.0906 Co: 0.0013 Feet [<------------------ Reaction Rate -----------:------->]
from Lab - Mn - Co - Co Midplane Sain pie#
+8.0 90-19llA 3.93E-18 5.50E-l8 2.llE-14
+7.5 90-19 l lB 5.97E-18 9.98E-18 2.43E- l4
+7.0 90-191 lC l.l4E-l7 l.83E- l 7 3~08E- l4
+6.5 90-191 lD l.09E-17 l.86E-l 7 3.09E-l4
+6.0 90-191 lE L6lE-l7 2.57E-l7 3.37E-14
+5.5 90-191 lF . 2.44E-17 3.61E-17 3.57E-14
+5.0 90-191 lG 2.90E-17 4.52E-17 3.92E-l4
+4.5 90-191 lH 3.20E-17 5.78E-17 4.20E-l4
+4.0 90-19111 3.69E-17 6.13E-17 4.45E-14
+3.5 90-191 lJ 4.42E-17 6.46E-17 4.73E-l4
+3.0 90-1911K 4.33E-17 6.87E-17 5.00E-14
+2.5 90-191 lL 4.51E-17 6.78E-17 5.18E-14
+2.0 90-191 lM
4.70E-17 7.35E-17 5.37E-14
+1.5 90-191 lN 4.64E-l7 6.89E-17 5.55E-14
+1.0 90-19110 4.88E-17 6.7.SE-17 5.70E-14
+0.5 90-191 lP 4.72E-17 6.91E-17 5.81E-14 0.0 90-191 lQ 4.92E-l7 7.50E-17 5.88E-14
-0.5 90-1911R 4.66E-17 7.22E-l7 5.90E-l4
-l.O 90-19115 4.74E-17 6.5 lE-17 5.86E-14
-1.5 90-191 lT 4.62E-17 6.72E-17 _5.76E-l4
-2.0 90-191 lU 4.50E-17 6.97E-17 5.7 lE-14
-2.5 90-1911V 4.46E-17 6.55E-l7 5.5 lE-14
-3.0 90-191 lW 3.99E-17 6.79E-17 5.41E-14
-3.5 90-191 lX 3.94E-17 6.13E-17 5.06E-l4
-4.0 90-191 lY 3.64E-17 5.46E-l7 4.8 lE-14
-4.5 90-191 lZ 3.07E-17 4.82E-l7 4.36E-l4 6-18
I Table 6-4 (Continued)
Reaction Rates Derived From the Long Stainless Steel Gradient Chains Irradiated During Cycle 8 Reference Azimuth: 210 deg. First Octant Equivalent Angle: 30 deg.
Bead Chain Tag ID: 210 Chain Composition Fe: 0.665 Ni: 0.0865 . Co: 0.0018 Feet [<------------------ Reaction Rate ------------------>]
from Lab - Mn - Co - Co Mid plane Sample#
+8.0 90-1912A 3.32E-18 5.52E-18 1.97E-14
+7.5 90-19128 4.91E-18 8.06E-18 2.27E-14
+7.0 90-1912C 6.71E-18 l.15E- l 7 2.6 lE-14
+6.5 90-19120 9.45E-18 1.79E- l 7 2.92E-14
+6.0 90-1912E l.59E-17 2.79E-17 3.15E-14
+5.5 90-1912F 2.18E-17 3.54E-l 7 3.39E-14
+5.0 90.:-19120 2.77E-17 4.64E-17 3.67E-14
+4.5 90-1912H 3.36E-17 5.61E-17 4.02E-14
+4.0 90-19121 3.69E-17 5.79E-17 4.26E-14
+3.5 90-19121 4.09E-17 6.2 lE-17 4.55E-14
+3.0 90-l 912K 4.18E-17 6.72E-17 4.68E-14
+2.5 90-1912L 4.68E-17 6.37E-l 7 4.90E-14
+2.0 90-1912M 4.35E-17 7. lOE-17 5.04E-14
+1.5 90-1912N 4.48E-17 6.98E-17 5.24E-14
+1.0 90-19120 4.42E-17 6.67E-17 5.35E-14
+0.5 90-1912P 4.49E-17 7.26E-17 5.45E-14 0.0 90-1912Q 4.26E-17 6.95E-17 5.68E-14
-0.5 90-1912R 4.69E-17 7. l lE-17 5.65E-14
-1.0 90-1912S 4.43E-17 7.03E-17 5.65E-14
-1.5 .90-1912T 4.45E-17 7.60E-17 5.56E-14
-2.0 90-19120 4.61E-17 7.13E-l 7 5.46E-14
-2.5 90-1912V 4. l.9E-17 6.49E-17 5.22E-14
-3.0 90-1912W 3.99E-17 6.21E-17 4.95E-14
-3.5 90-1912X 4.03E-17 5.96E-17 4.70E-14
. -4.0 90-1912Y 3.31E-17 5.64E-l 7 4.36E-14
-4.5 90-1912Z 2.71E-17 4.81E-17 3.95E-14 6-19
Table 6-4 (Continued)
Reaction Rates Derived From the Long Stainless Steel Gradient Chains Irradiated During Cycle 8 Reference Azimuth: 340 deg. First Octant Equivalent Angle: 20 deg.
Bead Chain Tag ID: 150 Chain Composition Fe: 0.684 Ni: 0.0941 Co: 0.0019 Feet [<------------------ Reaction Rate ----------------->]
from Lab - Mn - Co - Co Midplane Sample#
+8.0 90-1920A 4.89E-18 6.98E-18 1.92E-14
+7.5 90-19208 5.12E-18 l.27E-17 2. IOE-14
+7.0 90-1920C 8.49E-l 8 1.40E-17 2.43E-14
+6.5 90-19200 1.28E-17 1.94E-l 7 2.54E- l4
+6.0 90-1920E 1.68E-17 3.04E-17 2.95E-14
+5.5 90-1920F 2.49E-17 3.98E-17 3.08E-14
+5.0 90-1920G 3.08E-17 4.62E-17 3.42E-14
+4.5 90-1920H 3.54E-17 5.58E-17 3.70E-14
+4.0 90-19201 4.14E-17 5.85E-17 3.97E-14
+3.5 90-1920J 4.50E-17 6.30E-17 4.07E-14
+3.0 90-1920K 4.93E-17 6.77E-17 4.40E-14
+2.5 90-1920L 5.06E-17 7.22E-l 7 4.5 lE-14
+2.0 90-1920M 5.14E-l 7 7.37E-l 7 4.8 lE-14
+1.5 90-1920N 5.12E-17 7.33E-17 4.99E-14
+1.0 90-19200 4.79E-17 7.41E-17 5.07E-14
+0.5 90-1920P 4.94E-17 7.48E-17 5.32E-14 0.0 90-1920Q 5.19E-17 7.09E-l 7 5.43E- l4
-0.5 90-1920R 5.0IE-17 7.63E-17 5.37E-14
-1.0 90-19205 4.98E-17 7.70E-17 5.5 lE-14
-1.5 90-1920T 4.98E-l 7 7.94E-17 5.34E-14
-2.0 90-1920U 5.15E- l 7 7.78E-17 5.39E-14
-2.5 90-I9:iOV 5.06E-l 7 7.46E-17 5.23E-14
-3.0
-3.5
-4.0
-4.5 90-1920W 90-1920X 90-1920Y 90-1920Z 4.57E-17 4.34E-17 3.84E-l 7 1.26E-17 6.84E-17 5.99E-17 5.75E-17 1.77E- l 7 4.92E-14 4.83E-14 4.44E-14 l.46E-14 6-20
Table 6-4 (Continued)
Reaction Rates Derived From the Long Stainless Steel Gradient Chains Irradiated During Cycle 8 Reference Azimuth: 260 deg. First Octant Equivalent Angle: IO deg.
Bead Chain Tag ID: (NONE)
Chain Composition Fe: 0.672 Ni: 0.09 Co: 0.0017 Feet [<--------------- Reaction Rate --------------->]
from Lab - Mn - Co - Co Midplane Sample#
+8.0 90-l913A 4. l9E-18 7.78E-18 l.75E-l4
+7.5 90-l 913B 5.45E-18 9.09E-18 2.0 lE-14
+7.0 90-l913C 8.SOE-18 l.34E- l 7 2.l9E-l4
+6.5 90-1913D l.13E-17 l.52E-17 2.29E-14
+6.0 90-1913E 5.71E-l8 l.29E-l 7 2.08E-14
+5.5 90-1913F 3.43E-18 7.75E-18 l.87E-14
+5.0 90-l 913G 3.45E-18 5. l 9E-18 l.58E-14
+4.5 90-1913H 2.99E-18 3.39E- l 8 l.41E-14
+4.0 90-19131 l.74E-l8 2.57E-l8 l.34E-l4
+3.5 90-19131 l.l lE-18 2.89E-l8 l.09E- 14
+3.0 90-1913K l.07E-l8 2.43E-18 l.05E-l4
+2.5 90-l913L l.23E-18 l. l 9E- l 8 8.61E-l5
+2.0 90-1913M 8.07E-19 l .65E-l 8 7.69E-15
+l.5 90-1913N 8.43E-19 ND 6.37E-15
+l.O 90-19130 ND ND 5.39E-15
+0.5 90-1913P ND ND 4.57E-15 0.0 90-1913Q ND ND 4.09E-15
-0.5 90-1913R ND ND 3.60E-15
-l.O 90-1913S ND 4.66E-l 9 3.57E-l5
-1.5 90-1913T 3.76E-19 ND 3.2 lE-15
-2.0 90-19130 ND ND 2.99E-15
-2.5 90-l913V ND ND 2.76E-15
-3.0 90-1913W ND ND 2.66E- l5
-3.5 90-l913X ND ND - 2.46E- l5
-4.0 90-l9 l3Y ND ND 2.26E-l5
-4.5 90-19132 ND ND 2. l 8E- l5 6-21
Table 6-5 Average Reaction Rates Derived from the Three Symmetric 30 Degree Stainless Steel Gradient Chains Irradiated During Cycle 8 Average of Long Chains at 30°, 150°, and 2l0° Feet [<-------------------------- Average Reaction Rate -------------------------->]
from - Mn - Co - Co Mid plane rps/atom (lcr) rps/atom ( l cr) rps/atom ( l cr)
+8.0 3.38E-18 ( 15.8) 5.58E-18 (2.0) 2.04E-14 (3.4)
+7.5 4.90E-l8 (2 l. 9) 8.l5E-l8 (22.0) 2.30E- l4 (4.9)
+7.0 8.47E-18 (29.8) l.38E-17 (28.6) 2.77E- l4 (9.~)
+6.5 9.83E-l8* (9.4) l.69E- l 7 (14.l) 2.9 !E-14 (6.6)
+6.0 l.58E-l 7 ( l.9) 2.56E-l7 (9.3) 3.2 lE-14 (4.4)
+5.5 2. l 9E- l 7 (l l.0) 3.48E- l 7 (5.0) 3.38E-14 (5.7)
+5.0 2.74E-l7 (6.9) 4.35E--l 7 (9.0) 3.75E-l4 (3.8)
+4.5 3.23E-17 (3.6) 5.45E- l 7 (8.1) 4.05E-14 (3.3)
+4.0 3.58E-l7 (5.5) 5.7lE-l7 (8.l) 4.20E-l4 (6.6)
+3.5 4.l6E-17 (5.6) 6.23E-l7 (3.6) 4.54E- l4 (~.2)
+3.0 4.23E-17 (2.1) 6.60E-l 7 (5.2) 4.74E-l4 (4.9)
+2.5 4.53E-l7 (3. l) 6.46E-l 7 (4.4) 4.9 lE-14 (5.4)
+2.0 4.47E-l 7 (4.4) 6.86E-l7 (9.3) 5. l lE-14 (4.6)
+l.5 4.47E-17 (3.9) 6.74E-l7 (5.1) 5.28E-l4 (4.8)
+1.0 4.56E-17 (6.1) 6.68E-17 (0.8) 5.38E-14 (5.8)
+0.5 4.57E-l7 (2.8) 6.86E-17 (6.2) 5.52E-14 (4.8) 0.0 4.59E-l7 (7.2) 7.03E-l7 (6.3) 5.64E-14 (4.7)
-0.5 4.63E-17 ( 1.6) 7.02E-l 7 (3.8) 5.62E-14 (5.4)
-l.O 4.59E-17 (3.3) 6.76E-l 7 (3.9) 5.66E- l4 (3.6)
- l.5 4.46E-17 (3.3) 7.21E-l7 (6.2) 5.54E-l4 (4.3)
-2.0 4.57E-l7 ( l.3) 7.0lE-17 ( l.4) 5.49E-l4 (3.5)
-2.5 4.35E-l 7 (3.3) 6.67E-17 (3.8) 5.32E- l4 (3. l)
-3.0 4.06E-17 (3.l) 6.49E-l7 (4.5) 5. lOE-14 (5.3)
-3.5 4.00E-17 (1.2) 5.99E-l 7 (2. l) 4.85E-14 (3.9)
-4.0 3.53E-17 (5.4) 5.52E-l7 ( l.8) 4.55E-14 (5.2)
-4.5 2.90E-17 (6.1) 4.83E-l7 (0.6) 4.lOE-14 (5.5)
Values given in parenthesis are the standard deviations of the three measurements of each reaction at each axial location.
6-22
Table 6-6 Consumers Power Company Palisades Nuclear Plant Location of Cycle 9 Support Bar Mounted Dosimetry in the Reactor Cavity Reference First Bar Azimuthal Octant Shifted Core Midplane Core Bottom Location Equivalent Angle 270 deg 0 deg 6 deg Capsule A Capsule C 280 deg IO deg 16 deg . Capsule J 290 deg 20 deg 26 deg Capsule K Capsule L 300 deg 30 deg 36 deg Capsule F 315 deg 45 deg 39 deg Capsule N 330 deg 30 deg 24 deg Gradient Chain Only
Reference Bar Calculated Cycle 9 Reaction Rate Ratios Azimuthal Shifted Dosimeter (RR at R = !08" I RR at Dosimeter Radius)
Location Angle Radius 58 Ni {n,p) 58 Co 54Fe (n,p) 54Mn (degrees) (degrees) (inches) 270 6 100.7 0.936 0.936 280 16 101.6 0.906 0.906 290 26 102.5 0.940 0.940 300 36 103.5 . 0.974 0.974 315 39 105.3 0.990 0.990 330 24 107.6 0.996 0.996 6-23
-Table 6-7 Sum~ary of Reaction Rates Derived from Multiple Foil Sensor Sets Irradiated During Cycle 9 Reaction Rate (rps/nucleus)*
Capsule Capsule Capsule Capsule Capsule Capsule Reaction Acal cca) *J K L N 63 Cu (n.a) 7.57E-19 1.15E-l 9 7.06E-19 6.05E~l9 l.69E-19 4.19E--l 9
.i6Ti (n,p) l.07E-17 l.82E-l 8 1.02E-l 7 8.65E-18 2.59E-18 5.89E-18 s.iFe (n.p) 5.48E- l 7 9.58E-18 5.13E-l 7 4.28E-17 l.30E-17 2.96E-17 58 Ni (n,p) 7.44E-17 1.42E-l 7 7.25E-l 7 6.12E-17 l.99E-17 4.19E-17 238 U (n.f) 2.80E-16 5.53E-17 2.36E-16 2.19E-16 6.47E-17 1.41E-16 237Np (n,f)_ 4.24E-15 1.16E-15 4.00E-15 3.42E-15 l.36E-15 2.40E-15 59 Co (n,y)lbl 4.39E-14 2.22E-14 3.57E-14 3.20E-14 l.84E-14 3.55E-14 59 Co (n,y) 2.77E-14 1.46E-14 2.36E-14 2.28E-14 l.30E-14 2.23E-14 Capsule Identification Reference First Bar Azimuthal Octant Shifted Core Core Location Equivalent Angle Midplane Bottom 270 deg 0 deg 6 deg Capsule A Capsule C 280 deg 10 deg 16 deg Capsule J 290 deg 20 deg 26 deg Capsule K Capsule L 300 deg<c) 30 deg* 36 deg Capsule p<cl 315 deg 45 deg 39 deg Capsule N a) Capsules A and C were irradiated for both Cycle 8 and 9.
b) Bare foil, all others were cadmium shielded.
c) Note that the gradient chain and capsule at 300 degrees was mispositioned at the end of Cycle 8 and thus was not analyzed.
6-24
Table 6-8
Reaction Rates Derived From the Support Bar Mounted Stainless Steel Gradient Chains Irradiated During Cycles 8 and 9 Reference Azimuth: 270 deg. First Octant Equivalent Angle: 0 deg.
Bead Chain Tag ID: 270 Bar Shifted Angle: 6 deg.
Chain Composition Fe: 0.7088 Ni: 0.0977 Co: 0.0017 Feet [<------------------ Reaction Rate ------------------>]
from Lab - Mn - Co - Co Midplane Sample#
+0.5 92-712A 4.80E-17 7.09E-17 5.45E-14 0.0 Bare Foils 5.48E-17 7.44E-17 4.39E-14
-0.5 92-712C 4.66E-17 6.93E-17 5.43E-14
-1.0 92-7120 4.58E-17 6.73E-17 5.34E-14
-1.5 92-712E 4.46E-17 6.17E-17 5.19E-14
-2.0 92-712F 3.81E-17 6. lOE-17 5.lOE-14
-2.5 92-712G 3.57E-17 5.36E-17 4.71E-14
-3.0 92-712H 2.88E-17 4.44E-17 4.76E-14
-3.5 92-7121 2.72E-17 3.95E-17 4.44E-14
-4.0 92-7121 2.61E-17 3.60E-l 7 4.04E-14
-4.5 92-712K 1.60E- l 7 2.49E-17 3.3 lE-14
-5.0 92-712L l.12E-l 7 1.79E- l 7 . 2.94E-14
-5.5 Bare Foils 9.58E-18 l.42E-17 2.22E-14 6-25
Table 6-9 Reaction Rates Derived From the Support Bar Mounted Stainless Steel Gradient Chains Irradiated During Cycle 9 Reference Azimuth: 280 deg. First Octant Equivalent Angle: lO deg.
Bead Chain Tag ID: S-2 280 Bar Shifted Angle: 16 deg.
Chain Composition Fe: 0.7213 Ni: 0.0989 Co: (J.0014 Feet [<------------------ Reaction Rate ------------------>I from Lab - Mn - Co - Co Midplane Sample#
+0.5 92-713A 4.56E-17 6.85E-17 3.29E-l4 0.0 Bare Foils 5. l3E-17 7.25E-l 7 3.57E-14
-0.5
-l.0
-l.5
-2.0 92-713C 92-7130 92-713E 92-713F 4.61E-17 4.60E-17 4.38E-l7 4.05E-17 6.75E-l 7 6.56E-17 6.39E-l7 6.05E-l 7 3.30E-14 3.26E- l4 3.2 lE-14 3.13E-14
-2.5 92-7130 3.83E-17 5.67E-17 3.06E-14
-3.0 92-713H 3.42E-17 5.25E-17 2.94E- l4
-3.5 92-7131 3. l 9E-17 4.83E-17 2.79E-14
-4.0 92-7131 2.63E-17 4.0IE-17 2.64E-14
-4.5 92-713K l.92E-17 3.12E-l7 2.30E-l4
-5.0 92-713L l.37E-l7 2.17E-17 l.93E- l4
-5.5 92-713M l.OSE-17 l.60E-l 7 l.83E-14 6-26
Table 6-9 (Continued)
Reaction Rates Derived From the Support Bar Mounted Stainless Steel Gradient Chains Irradiated During Cycle 9 Reference Azimuth: 290 deg. First Octant Equivalent Angle: 20 deg.
Bead Chain Tag ID: S-2 290 Bar Shifted Angle: 26 deg.
Chain Composition Fe: 0.6913 Ni: 0.1018 Co: 0.()() 14 Feet [<------------~----- Reaction Rate ---~-------------->]
from Lab - Mn - Co - Co Midplane Sample#
+0.5 92-714A 4.04E-17 5.46E-17 3.0SE-14 0.0 Bare Foils 4.28E-17 6.12E-l 7 3.20E-14
-0.5 92-714C 4.14E-17 5.55E- l 7 3.12E-14
-1.0 92-7140 3.90E-17 5.53E-l 7 3.12E-14
-1.5 92-714E 4.07E-17 5.40E-l 7 3.07E-14
-2.0 92-714F 3.77E-17 5.22E- l 7 3.03E-14
-2.5 92-7140 3.56E-17 5.03E-17 2.94E-14
-3.0 92-714H 3.27E-l7 4.75E-17 2.89E-14
-3.5 92-7141 3.07E-17 4.48E-l 7 2.77E-14
-4.0 92-7141 2.86E-17 3.95E-l7 2.64E-14
-4.5 92-714K 2.34E-17 3.38E-17 2.48E-14
-5.0 92-714L l.63E-17 2.29E-l 7 2.00E-14
-5.5 Bare Foils l.30E-l 7 l.99E-17 l.84E-14 6-27
Table 6-9 (Continued)
Reaction Rates Derived From the Support Bar Mounted Stainless Steel Gradient Chains Irradiated During Cycle 9 Reference Azimuth: 315 deg. First Octant Equivalent Angle: 45 deg.
Bead Chain Tag ID: S-2 315 Bar Shifted Angle: 39 deg.
Chain Composition Fe: 0.7073 Ni: 0.1011 Co: 0.0014 Feet [<--------~--------- Reaction Rate --------~--------->]
from Lab - Mn - Co - Co Mid plane Sample#
+0.5 92-716A 2.75E-17 3.79E-l 7 3.36E- l4 0.0 Bare Foils 2.96E-17 4.19E-17 3.55E-14
-0.5 92-716C 2.78E-l 7 3.78E-17 3.39E- l4
-l.0 92-7160 2.72E-17 3.71E-17 3.35E-l4
-l.5 92-716E 2.40E-17 3.53E-17 3.3 lE-14
-2.0 92-716F 2.33E-17 3.41E-17 3.22E-14
-2.5 92-7160 2.20E-17 3.16E-l 7 3.13E-14
-3.0 92-716H 2.18E-l 7 3.00E-17 3.00E-14
-3.5 92-7161 l.95E-17 2.76E-17 2.86E-14
-4.0 92-716J l.64E- l 7 2.39E-17 2.67E-14
-4.5 92-716K l.41E-17 2.09E-l 7 2.45E- l4
-5.0 92-716L l.08E- l 7 l.5 lE-17 l.89E- l4
-5.5 92-716M 8.25E- l 8 l.l7E-l 7 l.65E-14 6-28
Table 6-9 (Continued)
Reaction Rates Derived From the Support Bar Mounted Stainless Steel Gradient Chains Irradiated During Cycle l)
Reference Azimuth: 330 deg. First Octant Equivalent Angle: 30 deg.
Bead Chain Tag ID: S-2 330 Bar Shifted Angle: 24 deg.
Chain Composition Fe: 0.7293 Ni: 0.104 Co: 0.0014 Feet [<------------------ Reaction Rate ------------------>]
from Lab - Mn - Co - Co Mid plane Sample#
+0.5 717A 3.83E- l 7 5.37E-l7 3.73E-14 0.0 92-717B 3.90E-l7 5.36E-l7 3.68E-14
-0.5 92-717C 3.75E-l7 5.30E-l7 3.7 IE-14
-l.O 92-7170 3.83E- l 7 5.26E-l7 3.67E-14
-l.5 92-7 l 7E 3.72E-l7 5.23E- l 7 3.61E-l4
-2.0 92-7 l7F 3.63E-l7 5.08E-l7 3.52E-l4
-2.5 92-7170 3.35E-l7 4.80E-l7 3.42E-14
-3.0 92-717H 3.l4E-l7 4.49E-l 7 3.27E-14
-3.5 92-7171 2.81E-17 4. lOE-17 3.08E-l4
-4.0 92-7171 2.42E-17 3.56E-17 2.87E-14
-4.5 92-717K l.94E- l 7 2.94E-l 7 2.64E-l4
-5.0 92-717L l.30E- l 7 l.95E- l 7 2.03E-14
-5.5 92-717M l.02E-l 7 l.43E-l 7 l.8 lE-14 6-29
Table 6-10 Reaction Rates Derived From the Long Stainless Steel Gradient Chains Irradiated During Cycle 9 Reference Azimuth: 30 deg. First Octant Equivalent Angle: 30 deg.
Bead Chain Tag ID: S-2 30 Chain Composition Fe: 0.7167 Ni: 0.0973 Co: 0.0013 Feet [<------------------ Reaction Rate ------------------->]
from Lab - Mn - Co - Co Mid plane Sample#
+8.0 92-707A 2.24E-18 3.68E-18 l.42E-14
+7.5 92-707B 3.12E-18 5.3_7E-18 l.62E-14
+7.0 92-707C 5.04E-18 8.18E-18 l.79E-14
+6.5 92-707D 7.70E-18 l.21E-17 l.94E-14
+6.0 92-707E l.13E-17 l.65E-17 2.08E-14
+5.5 92-707F l.47E-17 2.34E-17 2.28E-14
+5.0 92~707G l.89E-17 2.81E-17 2.47E-14
+4.5 92-707H 2.15E-17 3.33E-17 2.63E-14
+4.0 92-7071 2.SOE-17 3.68E-l 7 2.78E-14
+3.5 92-707J 2.70E-l 7 4.03E-17 2.91E-14
+3.0 92-707K 2.84E-l 7 4.14E-17 3.04E-14
+2.5 92-707L 2.95E-l 7 4.34E-17 3.14E-14
+2.0 92-707M 2.90E-17 4.45E-17 3.24E-14
+l.5 92-707N 3.00E-17 4.45E-17 3.36E-14
+l.O 92-7070 3.02E-17 4.53E-17 3.43E-14
+0.5 92-707P 3.09E-17 4.57E-17 3.53E-14 0.0 92-707Q 3.l lE-17 4.46E-17 3.55E-14
-0.5 92-707R 3.BE-17 4.55E-17 3.60E-14
-1.0 92-7075 3.00E-17 4.58E-17 3.59E-14
-1.5 92-707T 3.lOE-17 4.58E-17 3.59E-14
-2.0 92-707U 3.03E-17 4.59E-17 3.56E-14
-2.5 92-707V 2.98E-17 4.51E-17 3.47E-14
-3.0 92-707W 2.95E-17 4.24E-17 3.35E-14
-3.5
-4.0
-4.5 92-707X 92-707Y 92-707Z 2.56E-17 2.27E-17 2.0lE-17 3.89E-17 3.56E-17 2.99E-17 3.19E-14 2.99E-14 2.74E-14 6-30
Table 6-10 (Continued)
Reaction Rates Derived From the Long Stainless Steel Gradient Chains Irradiated During Cycle 9 Reference Azimuth: 90 deg. First Octant Equivalent Angle: 0 deg.
Bead Ch<:tin Tag ID: S-2 90 Chain Composition Fe: 0.7136 Ni: 0.0978 Co: 0.0014 Feet [<----------------- Reaction Rate ----------------->]
from Lab - Mn - Co - Co Midplane Srunple#
+8.0 92-708A 2.73E-18 4.62£-18 l.50E-14
+7.5 92-7088 4.23E-18 7.58£-18 l.75E-14
+7.0 92-708C 7.07E-18 l.08E-17 l.94E-14
+6.5 92-708D 1.07E-17 l.57E-17 2.14E-14
+6.0 92-708E l.54E-17 2.22E-17 2.32E-l4
+5.5 92-708F 2.0lE-17 2.95E-17 2.55E-14
+5.0 *92-708G 2.44E-17 3.69E-17 2.76E-14
+4.5 '92-708H 2.92E-17 4.38E-l7 2.98E-14
+4.0 92-7081 3.l3E-17 4.83E-l7 3.20E-l4
+3.5 92-7081 3.51E-17 5.21E-l7 3.37E-14
+3.0 92-708K 3.67E-17 5.47E-17 3.58E-l4
+2.5 92-708L 3.80E-l7 5.51E-l7 3.72E-14
+2.0 92-708M 3.80E-17 5.53E-17 3.73E-14
+1.5 92-708N 3.85E-17 5.64E-17 4.05E-14
+1.0 92-7080 3.97E-17 5.73E-17 4.18E-14
+0.5 92-708P 3.93E-17 5.70E-17 4.24E-l4 0.0 92-708Q 3.98E-17 5.62E-17 4.30E-14
-0.5 92-708R 3.96E-l7 5.60E-17 4.31E-l4
-1.0 92-708S 3.96E-17 5.55E-17 4.33E-J4
-1.5 92-708T 3.52E-17 5.28E-17 4.27E-14
-2.0 92-708U 3.44E-17 5.12E-17 4.18E-14
-2.5 92-708V 3.l6E-17 4.90E-17 4.00E-14
-3.0 92-708W 3.l7E-17 4.60E-17 3.84E-14
-3.5 92-708X 2.97E-17 4.30E-17 3.61E-l4
-4.0 92-708Y 2.63E-l 7 3.91E-l7 3.40E-14
-4.5 92-708Z 2.26E-l7 3.32E-l7 3.03E-14 6-31
Table 6-10 (Continued)
Reaction Rates Derived From the Long Stainless Steel Gradient Chains Irradiated During Cycle 9 Reference Azimuth: 150 deg. First Octant Equivalent Angle: 30 deg.
Bead Chain Tag ID: S-2 150 Chain Composition Fe: 0.7207 Ni: 0.0987 Co: 0.0014 Feet [ <----------------~ Reaction Rate ----------------->]
from Lab - Mn - Co - Co Mid plane Sample#
+8.0 92-709A 2.28E-18 3.69E-18 l.36E-14
+7.5 92-7098 3.SOE-18 5.24E-18 l.58E-14
+7.0 92-709C 5.67E-18 8.79E-18 l.83E-14
+6.5 92-709D 8.55E-18 l.26E-17 2.0lE-14
,. +6.0
+5.5
+5.0
+4.5 92-709E 92-709F 92-7090 92-709H l.12E-17 l.52E-17 l.90E-17 2.37E-17 l.76E-17 2.43E-l 7 2.99E-17 3.57E-17 2.17E-14 2.35E-14 2.52E-14 2.74E-14
+4.0 92-7091 2.55E-17 3.82E-17 2.93E-14
+3.5 92-7091 2.77E-17 4.38E-17 3.llE-14
+3.0 92-709K 2.91E-17 4.62E-17 3.26E-14
+2.5 92-709L 3.18E-17 4.78E-17 3.37E-14
+2.0 92-709M 3.21E-l 7 4.82E-17 3.50E-14
+1.5 92-709N 3.40E-17 4.85E-17 3.62E-14
+1.0 92-7090 3.17E-17 4.86E-17 3.72E-14
+0.5 92-709P 3.26E-17 4.99E-17 3.77E-14 0.0 92-709Q 3.3 lE-17 5.00E-17 3.83E-14
-0.5 92-709R 3.42E-17 5.03E-17 3.87E-14
-1.0 92-709S 3.43E-17 4.93E-17 3.81E-14
-1.5 92-709T 3.19E-17 4.81E-17 3.75E-14
-2.0 92-709U 3.24E-17 4.75E-17 3.80E-14
-2.5 92-709V 3.0BE-17 4.69E-17 3.65E-14
-3.0 92-709W 2.96E-17 4.SOE-17 3.57E-14
-3.5 92-709X 2.85E-17 4.28E-17 3.38E-14
-4.0 92-709Y 2.45E-17 3.84E-17 3.18E-14
-4.5 92-709Z 2.24E-17 3.22E-17 2.93E-14 6-32
Table 6-10 (Continued)
Reaction Rates Derived From the Long Stainless Steel Gradient Chains Irradiated During Cycle 9 Reference Azimuth: 260 deg. First Octant Equivalent Angle: 10 deg.
Bead Chain Tag ID: S-2 260 Chain Composition Fe: 0.7116 Ni: 0.0958 Co: 0.0014
Feet [<----------------- Reaction Rate ------------~---->]
from Lab - Mn - Co - Co Mid plane Sample#
+8.0 92-711A . 2.48E-l8 4.12E-18 l.52E-14
+7.5 92-7118 3.68E-18 6.29E-18 l.70E-14
+7.0. 92-711C 6.02E-18 9.58E-18 l.89E-14
+6.5 92-7110 9.52E-18 l.44E-17 2.08E-14
+6.0 92-711E lJlE-17 2.05E-17 2.25E-14
+5.5 92-711F l.83E-17 2.74E-17 2.42E-14
+5;o 92-7110 2.29E-17 3.61E-17 2.59E-l4
+4.5 92-711H 2.71E-17 4.22E-17 2.77E:l4
+4.0 92-7111 3.07E-17 4.72E-17 2.90E-14
+3.5 92-7111 3.34E-17 5.15E-17
3.03E-14
+3.0 92-711K 3.64E-17 5.41E-17 3.18E-14
+2.5 92-711L 3.78E-17 5.58E-17
3.28E-14
+2.b 92-711M 3.70E-17 5.61E-17 3.39E-14
+l.5 92-711N 3.73E-17 5.70E-17 3.47E-I4
+l.O 92-7110 3.92E-17 5.75E-17 3.57E-l4
. +0.5 92-711P 4.0lE-17 5.79E-17 3.63E-14 0.0 92-711Q 3.98E-17 5.83E-17 3.65E-14
-0.5 92-711R 3.98E-17 5.88E-17 3.70E-14
-1.0 92-711S 4.00E-17 5.93E-17 3.66E-14
-1.5. 92-711T 4.06E-17 - - 5.94E-17 3.62E -2.0 92-711U 3.94E-17 5.73E-17 3.56E-14
-2.5 92-711V 3.70E-17 5.47E-17 3.48E-14
-3.0 92-711W 3.49E-17 5.27E-17 3.33E-14
-3.5 92-711X 3.31E-17 4.87E-17 3.18E-14
-4.0 92-711Y 2.84E~17 4.41E-17 3.00E-14
-4.5 92-711Z 2.40E-17 . 3.74E-17 2.74E-14 6-33
Table 6-10 (Continued)
Reaction Rates Derived From the Long Stainless Steel Reference Azimuth: 340 deg.
Gradient Chains Irradiated During Cycle 9 First Octant Equivalent Angle: 20 deg.
Bead Chain Tag ID: S-2 340 Chain Composition Fe: 0.7001 Ni: 0.0999 Co: 0.0014 Feet [<----------------- Reaction Rate ----------------->]
from Lab - Mn - Co - Co Mid plane Sample#
+8.0 92-718A 2.74E-18 4.35E-18 l.46E-14
+7.5 92-718B - 3.91E-18 6.48E-18 l.63E-14
+7.0 92-718C 5.35E-18 9.66E-18 l.81E-14
+6.5 92-718D 9.40E-18 l.44E-17 2.0lE-14
+6.0 92-718E l.37E-17 2.06E-17 2.21E-14
+5.5 92-718F 1.85E-17 2.71E-17 2.43E-14
+5.0 92-7180 2.43E-17 3.50E-17 2.60E-14
+4.5 92-718H 2.89E-17 4.15E-17 2.79E-14
+4.0 92-7181 3.27E-17 4.60E-17 2.97E-14
+3.5 92-718J 3.49E-17 5.0lE-17 3.13E-14
+3.0 92-718K 3.65E-17 5.26E-17 3.27E-14
+2.5 92-718L 3.68E-17 5.38E-17 3.43E-14
+2.0 92-718M 3.84E-17 5.52E-17 3.58E-14
+1.5 92-718N 3.85E-17 5.60E-17 3.69E-14
+1.0 92-7180 3.92E-17 5.58E-17 3.80E-14
+0.5 92-718P 3.87E-17 5.60E-17 3.89E-14 0.0 92-718Q 4.05E-17 5.69E-17 3.92E-14
-0.5 92-718R 4.lOE-17 5.62E-17 3.98E-14
-1.0 92-718S 4.16E-17 5.69E-l 7 3.95E-14 *
-1.5 92-718T 4.12E-17 5.63E-17 3.93E-14
-2.0 92-718U 4.00E-17 5.63E-17 3.82E-14
-2.5 92-718V 3.79E-17 5.45E-17 3.72E-14
-3.0 92-718W 3.56E-17 5.l2E-17 3.59E-14
-3.5 92-718X 3.32E-17 4.76E-17 3.41E-14
-4.0 92-718Y 2.85E-17 4.20E-17 3.21E-14
-4.5 92-718Z 2.58E-17 3.58E-17 2.92E-14 6-34
Table 6-11 Palisades Cycle 8 Cavity Dosimetry 16° Midplane Results Comparison of Calculated and Measured Integral Quantities Ratio*. Uncertainty in Parameter Calculated Measured Cale/Meas Measured Value (lcr %}
Flux (E > 1.0 MeV) l.40E+09 l.46E+09 0.96 8 (n/cm 2-s)
Flux (E > 0.1 MeV) l.34E+l0 l.29E+l0 l.03 16 (n/cm 2-s)
Displacements per Atom per second 4.60E-12 4.49E-l2 1.03 13 (dpa/s)
Thennal Flux 2.66E+09 7.57E+08 3.52 36 (E < 0.414 eV) (n/cm 2 -s)
Total Flux 3.27E+l0 2.58E+l0 l.27 17 (n/cm 2 -s)
Comparison of Measured and Calculated Reaction Rates Reaction Rate (mslnucleus} Ratio Cale/Meas Reaction Measured Calculated Adjusted Calculated Adjusted Cu63(n,a)Co60 9.76E-19 l.18E-18 9.96E-19 l.21 1.02 Fe54(n,p)Mn54 7.42E-17 7.61E-17 7.42E-17 l.03 1.00 Ni58(n,p)Co58 l.04E-16 l.03E-16 l.02E-16 0.99 0.98 U238(n,f)F.P. (Cd) 4.14E-16 4.04E-16 4.13E-16 0.98 l.00 Ti46(n,p)Sc46 l.45E-l 7 l.46E-l 7 l.39E-l 7 l.00 0.96 Np237(n,t)F.P. 6.72E-15 6.62E-15 6.64E-15 0.99 0.99 Co59(n;y)Co60 4.71E-14 l.38E-13 4.95E-14 2.92 1.05 Co59(n,y)Co60 (Cd) 3.13E-14 6.88E-14 3. l lE-14 2.20 0.99 Average Ratio Cale/Meas for Threshold Reactions 1.03 0.99 6-35
Table 6-12 Palisades Cycle 8 Cavity Dosimetry 26° Midplane Results Comparison of Calculated and Measured Integral Quantities Ratio Uncertainty in Parameter Calculated Measured Cale/Meas Measured Value {lcr %}
Flux (E > 1.0 Me V)
J.11E+09 l.10E+09 1.01 8 (n/cm 2 -s)
Flux (E > 0.1 MeV) 1.14E+10 l.02E+10 1.12 17 (n/cm 2 -s)
Displacements per Atom per second 3.86E-12 3.50E-12 1.10 13 (dpa/s)
Thermal Flux 2.47E+09 6.76E+08 3.65 38 (E < 0.414 eV) (n/cm 2-s)
Total Flux 2.90E+10 2.15E+l0 1.35 17 (n/cm 2-s)
Comparison of Measured and Calculated Reaction Rates Reaction Rate (d12slnucleus} Ratio Cale/Meas Reaction Measured Calculated Adjusted Calculated Adjusted Cu63(n,a)Co60 7.5 lE-19 9.25E-19 7.67E-19 1.23 1.02 Fe54(n,p)Mn54 5.60E-17 5.88E-17 5.60E-17 1.05 1.00 Ni58(n,p)Co58 7.81E-17 7.98E-17 7.70E-17 1.02 0.99 U238(n,f)F.P. (Cd) 3.19E-16 3.16E-16 3.12E-16 0.99 0.98 Ti46(n,p)Sc46 1.1 lE-17 1.l 3E-17 1.07E-17 1.02 0.96 Np237(n,f)F.P. 4.97E-15 5.45E-15 5.0lE-15 1.10 1.01 Co59(n;y)Co60 4.41E-14 1.27E-13 4.65E-14 2.87 1.05 Co59(n;y)Co60 (Cd) 3.04E-14 6.28E-14 3.00E-14 2.07 0.99 Average Ratio Cale/Meas for Threshold Reactions 1.07 0.99 6-36
Table 6-13
. Palisades Cycle 8 Cavity Dosimetry 26° Core Bottom Results Comparison of Calculated and Measured Integral Quantities Ratio Uncertainty in Parameter Calculated Measured Cale/Meas Measured Value {lcr %}
Flux (E > 1.0 MeV) 3.32E+08 3.86E+08 0.86 8 (n/cm 2-s)
Flux (E > 0, 1 MeV) 3.42E+09 3.76E+09 0.91 17 (n/cm 2-s)
Displacements per Atom per second 1.16E-12 l.28E-12 0.91 13 (dpa/s)
Thermal Flux 7.40E+08 3.49E+08 2.12 39 (E < 0.414 eV) (n/cm 2-s)
Total Flux 8.70E+09 8.35E+09 1.04 16 (n/cm 2-s)
Comparison of Measured and Calculated Reaction Rates Reaction Rate (dQslnucleus) Ratio Cale/Meas Reaction Measured Calculated Adjusted Calculated Adjusted Cu63(n,a.)Co60 2.00E-19 2.77E-19 2.08E-19 1.39 1.04 Fe54(n,p)Mn54 1.68E-17 1.76E-17 1.71E-l 7 1.05 1.02 Ni58(n,p)Co58 2.58E-17 2.39E-17 2.45E-17 0.93 0.95 U238(n,t)F.P. (Cd) 1.09E-16 9.47E-17 1.06E-16 0.87 0.97 Ti46(n,p)Sc46 3.35E-18 3.40E-18 3.14E-18 1.02 0.94 Np237(n,t)F.P. 1.86E-15 1.63E-15 1.86E-15 0.88 1.00 Co59(n;y)Co60 2.53E-14 3.80E-14 2.62E-14 1.50 1.04 Co59(n,y)Co60 (Cd)* 1.78E-14 l.88E-14 1.74E-14 1.06 0.98.
Average Ratio Cale/Meas for Threshold Reactions 1.02 0.99 6-37
Table 6-14 Palisades Cycle 8 Cavity Dosimetry 39° Midplane Results Comparison of Calculated and Measured Integral Quantities Ratio Uncertainty in Parameter Calculated Measured Cale/Meas Measured Value [lcr %}
Flux (E > 1.0 MeV) 8.16E+08 7.62E+08 1.07 8 I (n/cm 2-s)
,. Flux (E > 0.1 MeV) 9.27E+09 7.89E+09 1.18 17 (n/cm 2-s)
Displacements per Atom per second 3.09E-12 2.66E-12 1.16 14 (dpa/s)
Thermal Flux 2.36E+09 8.56E+08 2.76 33 (E < 0.414 eV) (n/cm 2-s)
Total Flux 2.56E+l0 l.86E+l0 1.38 17 (n/cm 2-s)
Comparison of Measured and Calculated Reaction Rates Reaction Rate (d12sLnucleus) Ratio Cale/Meas**
Reaction Measured Calculated Adjusted Calculated Adjusted Cu63(n,a.)Co60 5.53E-19 6.82E-19 5.64E-19 1.23 1.02 Fe54(n,p)Mn54 4.00E-17 4.29E-17 3.98E-17 1.07 0.99 Ni58(n,p)Co58 5.5 lE-17 5.83E-17 5.44E-l 7 1.06 0.99 U238(n,f)F.P. (Cd) 2.16E-16 2.32E-16 2. l 7E-16 1.07 1.01 Ti46(n,p)Sc46 7.89E-18 8.29E-18 7.61E-18 1.05 0.97 Np237(n,f)F.P. 3.65E-15 4.23E-15 3.67E-15 1.16 1.01 Co59(n,y)Co60 4.90E-14 1.22E-13 5.05E-14 2.49 1.03 Co59(n,y)Co60 (Cd)* 2.95E-14 6.06E-14 2.96E-14 2.05 1.00 Average Ratio Cale/Meas for Threshold Reactions 1.11 1.00 6-38
Table 6-15 Palisades Cycle 8-9 Cavity Dosimetry 6° Midplane Results Comparison of Calculated and Measured Integral Quantities Ratio Uncertainty in Parameter Calculated Measured Cale/Meas Measured Value (lcr %2 Flux (E > 1.0 Me V)
(n/cm 2 -s) 1.01E+09 9.81E+08 1.03 8 *I Flux (E > 0.1 MeV) l.03E+10 8.88E+09 1.16 17 (n/cm 2 -s) I Displacements per Atom per_second 3.49E-12 3.09E-12 1.13 13 (dpa/s)
Thermal Flux 2.24E+09 7.31E+08 3.06 35 (E < 0.414 eV) (n/cm 2 -s)
. Total Flux 2.63E+10 l.93E+10 1.36 17 (n/cm2 -s)
Comparison of Measured and Calculated Reaction Rates
- Reaction Rate !mslnucleus} Ratio Cale/Meas Reaction Measured Calculated Adjusted Calculated Adjusted Cu63(n,a)Co60 7.57E-19 8.89E-19 7.73E-19 1.17 1.02 Fe54(n,p)Mn54 _ 5.48E-17 5.50E-17 5.41E-17 1.00 0.99 I Ni58(n,p)Co58 7.44E-17 7.44E-17 7.34E-17 1.00 0.99 I U238(n,t)F.P. (Cd) . 2.80E-16 2.90E-16 2.84E-16 1.04 1.02 Ti46(n,p)Sc46 l.07E-17 l.08E-l 7 1.04E-17 1.01 0.97 Np237(n,t)F.P. 4.24E-15 4.76E-15 4.27E-15 1.12 1.01 Co59(n;y)Co60 4.39E-14 1.16E-13 4.56E-14 2.65 1.04 Co59(n,y)Co60 (Cd) 2.77E-14 5.77E-14 2.76E-14 2.08 1.00 Average Ratio Cale/Meas for Threshold Reactions 1.06 1.00 6-39
Table 6-16 Palisades Cycle 8-9 Cavity Dosimetry 6° Core Bottom Results Comparison of Calculated and Measured Integral Quantities Ratio Uncertainty in Parameter Calculated Measured Cale/Meas Measured Value {lcr %2 Flux (E > l.0 MeV) l.77E+08 2.18E+08 0.81 8 (n/cm 2 -s)
Flux (E > 0.1 MeV) l.80E+09 2.32E+09 0.77 17 (n/cm 2 -s)
Displacements per Atom per second 6.12E-13 7.74E-13 0.79 14 (dpa/s)
Thermal Flux I (E < 0.414 eV) (n/cm 2 -s) 3.92E+08 3.09E+08 l.27 36 Total Flux I (n/cm 2 -s) 4.60E+09 5.47E+09 0.84 16 Comparison of Measured and Calculated Reaction Rates Reaction Rate (rnsLnucleus} Ratio Cale/Meas Reaction Measured Calculated Adjusted Calculated Adjusted Cu63(n,a.)Co60 l.15E-19 l.56E-19 1.19E-19 l.35 l.04 Fe54(n,p)Mn54 9.58E-18 9.62E-18 9.57E-18 l.00 l.00 Ni58(n,p)Co58 l.42E-l 7 l.30E-l 7 l.36E-17 0.92 0.96 U238(n,f)F.P. (Cd) 5.53E-17 5.08E-17 5.79E-17 0.92 1.05 Ti46(n,p )Sc46 l.82E-18 l.89E-18 l.73E-18 1.04 0.96 Np237(n,t)F.P. l.16E-15 8.34E-16 l.12E-15 0.72 0.96 Co59(n;y)Co60 2.22E-14 2.04E-14 2.25E-14 0.92 1.0 l Co59(n,y)Co60 (Cd) 1.46E-14 1.0 lE-14 l.43E-14 0.69 0.98 Average Ratio Cale/Meas for Threshold Reactions 0.99 1.00 6-40
Table 6~ 17 Palisades Cycle 9 Cavity Dosimetry 16° Midplane Results Comparison* of Calculated and Measured Integral Quantities Ratio Uncertainty in Parameter Calculated Measured Cale/Meas Measured Value (lcr %~
Flux (E > 1.0 MeV)
(n/cm 2-s) 9.60E+08 8.92E+08 1.08 8
. Flux (E > 0. I MeV) 9.31E+09 8.01E+09 1.16 17 (n/cm 2-s)
Displacements per Atom per second . 3.19E-12 2.79E-12 1.15 13 (dpa/s)
Thermal Flux l.85E+09 5.65E+08 3.28 36 (E < 0.414 eV) (n/cm 2 -s) I Total Flux 2.28E+l0 l.69E+l0 1.35 17 (n/cm2-s) I Comparison of Measured and Calculated Reaction Rates Reaction Rate (dQs[nucleus} Ratio Cale/Meas Reaction Measured Calculated Adjusted Calculated Adjusted Cu63(n,a)Co60 7.06E-19 8.61E-19 7.24E-19 1.22 1.03 I Fe54(n,p)Mn54 5.13E-17 5.32E-17 5.06E-17 1.04 0.99.
Ni58(n,p)Co58 7.25E-17 7.20E-17 6.95E-17 0:99 0.96 U238(n,t)F.P. (Cd) 2.36E-16 2.78E-16 2.58E-16 1.18 1.09 Ti46(n,p)Sc46 l.02E-17 l.05E-17 9.86E-18 1.03 0.97 Np237(n,t)F.P. 4.00E-15 4.41E-15 3.94E-15 1.10 0.98 Co59(n,y)Co60 . 3.57E-14 9:65E-14 3.73E-14. 2.70 1:05 1-Co59(n,y)Co60 (Cd) 2.36E-14 4.80E-14 2.34E-14 2.03 0.99 I
Average Ratio Cale/Meas for Threshold Reactions 1.09 1.00 6-41
Table 6-18 Palisades Cycle 9 Cavity Dosimetry 26° Midplane Results Comparison of Calculated and Measured Integral Quantities Ratio Uncertainty in Parameter Calculated Measured Cale/Meas Measured Value (lcr %)
Flux (E > l.0 MeV) 8.20E+08 7.77E+08 l.06 8 (n/cm 2-s)
Flux (E > 0.1 MeV) 8.33E+09 7.14E+09 l.17 17 (n/cm 2-s)
Displacements per Atom per second 2.83E-12 2.47E-12 l.15 13 (dpa/s)
Thennal Flux I (E < 0.414 eV) (n/cm 2-s) l.80E+09 4.68E+08 3.85 39
,, Total Flux 2.12E+l0 l.54E+l0 l.38 17 (n/cm 2-s)
Comparison of Measured and Calculated Reaction Rates Reaction Rate (dQsLnucleus) Ratio Cale/Meas Reaction Measured Calculated Adjusted Calculated Adjusted Cu63(n,a.)Co60 6.05E-19 7.30E-19 6.18E-19 l.21 l.02 Fe54(n,p)Mn54 4.28E-17 4.50E-17 4.27E-17 l.05 l.00 Ni58(n,p)Co58 6.12E-17 6.08E-17 5.90E-l 7 0.99 0.96 U238(n,t)F.P. (Cd) 2.19E-16 2.36E-16 2.25E-16 l.08 l.03 Ti46(n,p )Sc46 8.65E-18 8.84E-18 8.34E-18 l.02 0.96 Np237(n,t)F.P. 3.42E-15 3.86E-15 3.43E-15 1.13 1.00 Co59(n,y)Co60 3.20E-14 9.30E-14 3.39E-14 2.90 1.06 Co59(n,y)Co60 (Cd)
2.28E-14 4.58E-14 2.24E-14 2.01 0.98 Average Ratio Cale/Meas for Threshold Reactions 1.08 1.00 6-42
Table 6-19 Palisades Cycle 9 Cavity Dosimetry 26° Core Bottom Results
')
Comparison of Calculated and Measured Integral Quantities Ratio Uncertainty in Parameter Calculated Measured Cale/Meas Measured Value (lcr %]
Flux (E > 1.0 MeV) 2.50E+08 2.64E+08 0.95 8 (n/cm 2-s) I Flux (E > 0.1 MeV) 2.54E+09 2.73E+09 0.93 17 (n/cm 2 -s) I Displacements per Atom per second 8.65E-13 9. l 7E-13 0.94 14 (dpa/s)
Thermal Flux 5.50E+08 2.50E+08 2.20 39 (E < 0.414 eV) (n/cm 2-s) I Total Flux 6.46E+09 6.19E+09 1.04 16 (n/cm2 -s) I Comparison of Measured and Calculated Reaction Rates Reaction Rate (rnsLnucleus) Ratio Cale/Meas Reaction Measured Calculated Adjusted Calculated Adjusted Cu63(n,a)Co60 l.69E-19 2.23E-19 1.75E-19 1.32 1.03 Fe54(n,p)Mn54 1.30E-17 l.37E-l 7 l.30E-17 1.06 1.00 Ni58(n,p)Co58 1.99E-l 7 1.86E-l 7 1.85E- l 7 0.93 0.93 U238(n,f)F.P. (Cd) 6.47E-17 7.21E-17 7.20E-17 1.11 1.11 Ti46(n,p)Sc46 2.59E-18 2.70E-18 2.47E-18 1.04 0.96 Np237(n,f)F.P. 1.36E-15 l.18E-15 l.31E-15 0.86 0.96 Co59(n;y)Co60 l.84E-14 2.84E-14 l.9 lE-14 1.55 1.04 Co59(n,y)Co60 (Cd) l.30E-14 l.40E-14 l.27E-14 1.08 0.98 Average Ratio Cale/Meas for Threshold Reactions 1.05 1.00 6-43
J.
Table 6-20 Palisades Cycle 9 Cavity Dosimetry 39° Midplane Results Comparison of Calculated and Measured Integral Quantities Ratio Uncertainty in Parameter Calculated Measured Cale/Meas Measured Value (lcr %2 Flux (E > 1.0 MeV) 6.12E+08 5.26E+08 l.16 9 (n/cm 2-s)
Flux (E > 0.1 MeV) 6.86E+09 5.34E+09 1.29 17 (n/cm 2 -s)
Displacements per Atom per second 2.29E-12 l.82E-12 1.26 14 (dpa/s)
Thennal Flux I (E < 0.414 eV) (n/cm 2 -s)
I.74E+09 5.89E+08 2.96 34
I Total Flux (n/cm 2 -s) l.89E+l0 l.30E+l0 Comparison of Measured and Calculated Reaction Rates 1.46 17 Reaction Rate (dQsLnucleus) Ratio Cale/Meas Reaction Measured Calculated Adjusted Calculated Adjusted Cu63(n,a)Co60 4.19E-19 5.21E-19 4.28E-19 1.24 l.02 Fe54(n,p)Mn54 2.96E-17 3.25E-17 2.93E-l 7 l.10 0.99 Ni58(n,p)Co58 4.19E-17 4.40E-17 4.03E-17 l.05 0.96 U238(n,f)F.P. (Cd) l.41E-16 l.74E-16 l.52E-16 l.24 1.08 Ti46(n,p)Sc46 5.89E-18 6.31E-18 5.7 lE-18 l.07 0.97 Np237(n,f)F.P. 2.40E-15 3.03E-15 2.42E-15 l.26 l.01 Co59(n,y)Co60 3.55E-14 9.04E-14 3.68E-14 2.55 l.04 Co59(n;y)Co60 (Cd) 2.23E-14 4.47E-14 2.22E-14 2.01 l.00
Average Ratio Cale/Meas for Threshold Reactions l.16 l.0 l 6-44
Height Cycle 8 Table 6-21 Palisades Cavity Axial Flux Profile Cycle 9 Average ft. Rel. Flux Std.% Rel. Flux Std.% ~Cle 8-9 8.0 0.080 13.9 0.068 5.2 0.074 7.5 0.106 12.5 0.101 6.2 0.102 7.0 0.181 17.4 0.160. 10.9 0.169 6.5 0.235 11. l 0.250 6.2 0.237 6.0 0.356 7.2 0.353 7.2 0.348 5.5 0.488 5.9 0.473 5.0 0.473 5.0 0.605 3.6 0.597 3.7 0.591 4.5 0.715 4.1 0.711 3.6 0.701 4.0 0.799 4.0 0.792 2.6 0.782.
3.5 0.907 1.9 0.861 3.2 0.872 3.0 0.941 2.4 0.910 2.6 0.911 2.5 0.993 3.3 0.949 2.6 0.957 2.0 0.990 2.0 0.952 2.2 0.957 1.5 0.984 2.5 0.974 3.3 0.962 1.0 0.975 3.6 0.981 2.5 0.960 0.5 b.993 1.0 0.990 2.2 0.974 0.0 1.028 4.4 1.005 1.2 1.000
-0.5 1.015 2.3 1.014 1.2 0.997
-1.0 0.989 2.6 1.010 2.2 0.980
-1.5 0.975 1.8 0.981 4.1 0.960
-2.0 0.988 4.9 0.963 3.9 0.960
-2.5 0.956 3.5 0.914 5.5 0.922
-3.0 0.872 6.3 0.883 5.0 0.861
-3.5 0.871 2.8 0.820 3.6 0.834
-4.0 0.762 3.7 0.713 3.1 0.728
-4.5 0.549 27.3 0.628 5.2 0.573
Note: Height is provided relative to the axial midplane of the active core.
6-45
Figure 6-1 Palisades Cycle 8 Palisades Cycle 8 Fe-54(n,p )Mn-54 Reaction Rate vs Angle 6
5 4
OTC cula on 0 ort radie t Ch s
v ng G a die n Fo s Ch. s 3
-5 0 5 10 15 20 .25 30 35 40 45 50 Azimuthal Angle (degrees)
Chain Data Fit at Z=O Bar Shifted 6 deg 6-46
. Figure 6-2 I
Palisades Cycle 8 Palisades Cycle 8 Ni-58(n,p )Co-58 Reaction Rate vs Angle
-r-
...-4 I
10 i::c:i 0 9
...-4 rll Q) B s
~
E-t 7
Q)
~
<<S
~
6
~
0
~
~
C)
<
~~s o.-j E-t~~
~~......_, 5 CL>~~
~
~
~~0::~~
~~i::~~
~~0 4~~
~~.-j~~
~
0
~ .92 CL>
0:: 0
~~v 3 ..........................._.__._._.._._._._._........._.__._._.._._......._.........................._._._._.'-'-'........................._._.__._..................................._._._.._._.~~
-5 0 5 10 15 20 25 30 35 40 45 50 Azimuthal Angle (degrees)
Chain Data Fit at Z=O Bar Shifted 6 deg 6-48
~~. Figure 6~4 Palisades Cycle 8 Palisades Cycle 8 Ni-58(n,p)Co-58 Reaction Rate vs Angle 10 9~~
B
' 7 6
5 OTC .98 0 s
v
4
-5 0 5 10 15 20 25 30 35 40 45 50 Azimuthal Angle (degrees)
Cham Data Fit at Z=O Bar Shifted* 6 deg 6-49
Figure 6-5 Palisades Cycle 8 Palisades Cycle* 8 - Short Chains Fe-54 (n,p) Mn-54 Reaction Rate vs Z 9
f;::::
I Ll.J q
a-1 deg
+-2 deg
~~- deg~~
~~-2 deg a.a 5 -3 -2 -1 0 Feet from Core Midplane 6-50~~
~~Figure 6-6 Palisades Cycle 8 Palisades Cycle 8 - Short Chains Ni-58 [n,p) Co-58 Reaction Rate vs Z 13~~
'O
~ I l..L.J 9
~~a-1 deg~~
~~+-2 deg~~
~~- deg 1-2 deg 1~~
~~5 -3 -2 -1 0 Feet from Core Midplane 6-51~~
~~Figure 6-7 Palisades Cycle 8 Palisades Cycle 8 - Short Chains Co-59 (n,r) Co-60 Reaction Rate vs Z 6~~
5
9

I LL.J q 4 lfi E
I=
Q) 0a:::
c:
.Q *3 i'
a:::
a-1 deg
+-2 deg
~~- deg~~
~~-2 deg 2~~
5 -3 -2 -1 0 Feet from Core ~dplane 6-52
Figure 6-8 Palisades Cycle 8 Palisades Cycle 8 - Long Chains Fe-54 (n,p) Mn-54 Reaction Rate vs Z 6
5 r-I LJ..J q
.,...... 4
~
E F
Q) 0 0:::
c:
0
~~.;::; 3 a 0 deg~~
~
0:::
+ 20 deg I) deg
~~g 2~~
~~3 -2 -1 0 2 3 5 6 Feet from Core Midplane 6-53~~
~~Figure 6-9 Palisades Cycle 8 Palisades Cycle 8 - .Long Chains Ni-58 (n,p) Co-58 Reaction Rate vs Z 9~~
a 7
r-I LU a
....... 6 fa E
~
C1' 0 5 0:::
c:
0 a Odeg
~ + 20 deg 0:::
4
~~Il li!g g 3~~
3 -2 -1 0 2 5 6 Feet from Core Midplane 6-54
Figure 6-10 Palisades Cycle 8 Palisades Cycle 8 - Long Chains Co-59 (n,r) Co-60 Reaction Rate vs Z 7
B
~
I L.i.J CJ 5
I-=
~
.s 0 a:::
c:
ia:::
4 a-
+-
3 3 -2 ~ a 1 2 3 4 5 B Feet from Core Midplane 6-55
~~Figure 6-11 Palisades Cycle 8 Palisades Cycle 8 - Long Chains Fe-54 (n,p) Mn-54 Reaction Rote vs Z 6~~
5 D r-I l.J....I 0
........ 4
~~{5 E~~
I=
co 00:::
c:
~
0 3 a 0 !Ilg
~
0:::
2 3 -2 -1 0 2 3 5 6 Feet from Core Midplane 6-56
~~Figure 6-12 Palisades Cycle 8 Palisades Cycle 8 - Long Chains Fe-54 (n,p) Mn-54 Reaction Rate vs Z B~~
5
~c:
0
] + 20 deg 2'--~-'--~-'-~-'-~-'-~-'-~-'-~--'~~'--~-'--~-'---'~
-5 -3 -2 -1 0 2 3 5 B Feet from Core Midplone 6-57
~~Figure 6-13 Palisades Cycle 8 Palisades Cycle 8 - Long Chains Fe-54 (n,p) Mn-54 Reaction Rate vs Z B~~
5 r-
..-- I Ll..J s 4 gs E
!-=
Q;I 15 a:::
c:
0
~ 3
~
a:::
~~Il cEg g 2~~
~~3 -2 -1 0 2 3 5 B Feet from Core Midplane 6-58~~
~~Figure 6-14 Palisades Cycle 8 Palisades Cycle B - Long Chains Ni-58 (n,p) Co-58 Reaction Rate vs Z g~~
B 7
r-I L.LJ s 6 fa E
I=
cu*
-s 5 ct::
c 0
c Odeg*
~
4 3
-5 '-4 2 -1 0 ' 2 4 5 6 Feet from ~re Midplane 6-59
~~Figure 6-15 Palisades Cycle 8 Palisades Cycle 8 - Long Chains Ni-58 (n,p) Co-58 Reaction Rote vs Z 9~~
8 +
7 r--
...--I lJ..J
~~3 B ffi E~~
i=
~
15 5 0::
c:
0
~ + 20 deg 0::
3 3 -2 -1 0 2 5 B Feet from Core Midplane 6-60
Figure 6-16 Palisades Cycle 8
- I I
- I Palisades Cycle 8 - Long Chains Ni-58 (n,p] Co-58 Reaction Rate vs Z Q
8 7
r--
I L&.J
~~3 B lB E~~
I=
Q) 0 5 c::
c:
0 c::
~
4
~~Il cEg g 3~~
3 -2 -1 0 2 3 5 Feet from Core Midplane 6-61
Figure 6-17 Palisades Cycle 9 Palisades Cycle 9 Fe-54(n,p )Mn-54 Reaction Rate vs Angle
-r--
..-4 I
5 Pi:l 0
..-4 fll Q) 4 s
~~.-I E-t Q)~~
~
a:S
~
.~
0
~~.-I~~
~
(,)
a:S Q)
OTC cula ion
~ o ort rad.ie t Ch s
ng G adie Chai s v n Fo s 2~_._.............................................................................................................................................................................................................................~...............
-5 0 5 10 15 20 25 30 35 40 45 50 Azimuthal Angle (degrees)
Chail;l Data Fit at Z=O Bar Shifted 6 deg 6-62
Figure 6-18 Palisades Cycle 9 Palisades Cycle 9 Ni-58(n,p )Co-58 Reaction Rate vs Angle 7
I 6 I OTC cula ion O ort rad.le t Ch s
~~ng G adie Ch~~
s v are N ckel oils 3~.........................~........................~..............................................._._._._._......_.._._...................................................._._._...................................
-5 0 5 10 .15 20 25 30 35 40 45 50 Azimuthal Angle (degrees)
Chain Data Fit at Z=O Bar Shifted 6 tj.eg 6-63
Figure 6-19 Palisades Cycle 9 Palisades Cycle 9 Fe-54(n,p)Mn-54 Reaction Rate vs Angle
-z:-..
...-4 I
5
.~
0
...-4 I'll Q,) 4 s
~~.-1 E-t Q,)~~
~
<
< 1.0 MeV) and (E > 0.1 MeV), and iron atom displacement rate (dpa/sec) are compared with the results of the FERRET least squares adjustment procedure; while, in the second case, calculations of individual sensor reaction rates* are compared directly with the measured data from the counting laboratory. It is shown that these two levels of comparison yield consistent and similar results, indicating that die least squares adjustment methodology is producing accurate exposure results and that the calculation to measurement comparisons are yielding accurate bias factors that can be applied to the neutron transport cak:ulations performed
~~for the Palisades reactor.~~
7-1
7-1. Comparison of Least Squares Adjustment Results with Calculation In Table 7-1. comparisons of calculated (DOT R-0) and. measured (adjusted results from FERRET) fast neutron exposure rates are given for the dosimetry sets. These data are seen to provide a consistent set. of comparisons that indicate the* adequacy and bias of the calculated fluence. Based on an average of all of this core midplane data, the calculated fast neutron flux (E > 1.0 Me V) overpredicted the measurements by an average factor of 1.09 for the in-vessel dosimetry and 1.03 for the ex-vessel dosimetry. It should be noted that the calculated flux values are slightly different from those in the tables in Sections 5 and 6. This is because of round-off error in converting to the FERRET group structure and, in the case of the reactor cavity spectra, due to a slight difference in position for the spectrum used as input. These differences have negligible effect on the flux derived by FERRET'.
The two in-vessel C/M ratios agree almost exactly even though the first covered an irradiation period of Cycles 1-5 and the other an entirely different fuel loading scheme in Cycle 9. The ex-vessel dosimetry ratios for fast neutron flux (E > 1.0 MeV) have a standard deviation of 0.06.
which is consistent with the expected value based on the FERRpT analysis (each derived flux
~~value has about an eight percent uncertainty). Similar conclusions can be drawn for the fast neutron flux (E > 0.1 Me V) and the iron atom displacement rate.~~
An inspection of the reactor cavity dosimetry comparisons in Table 7-1 indicates that there may be some differences in bias at the various angles and there may also be a slight difference between Cycle 8 and Cycle 9, but the differences are not significant compared to the estimated uncertainties. For this reason, it is concluded that the best approach for determining the reactor vessel exposure is to use an average bias value. Since the errors in extrapolation to the vessel from the in-vessel and ex.:vessel dosimetry locations are largely uncorrelated, the simple average of the in-vessel bias ( 1.09) and the ex-vessel bias ( 1.03) is taken as the best estimate of the calculation bias (1.06) for determination of the vessel exposure. Using the detailed uncertainty estimates from Reference 15, it is concluded that the uncertainty in this average bias factor of 1.06 is ten percent.
The results in Table 7-1 for fast neutron flux (E > 0.1 Me V) and for iron atom displacement rate
~~indicate little difference in bias inside the vessel, but an increase outside the vessel. This can be taken to indicate that the calculation is not predicting the neutrons with energies below 1.0 Me V~~
~~as accurately in the reactor cavity. This could be due to the approximations made in treating the cavity in two dimensions and may not indicate any error in the neutron transport in the vessel.~~
~~7-2~~
~~For conservatism, therefore, the fluence (E > 0.1 MeV) and tron dpa m the vessel will be assumed to have the same bias as the fluence (E > 1.0 Me V).~~
7-2. Comparisons of Measured and Calculated Sensor Reaction Rates In Tables 5-5 and 6-11 through 6-20, calculation to measurement ratios for each neutron sensor reaction rate from the in-vessel dosimetry capsule and reactor cavity irradiations are listed (based on the slightly modified spectrum in the FERRET group structure). For the midplane dosimetry
sets, the a priori C!M ratio tabulation provides a direct comparison, on an absolute basis, of calculation and measurement prior to the application of the least squares adjustment procedure as represented in the FERRET evaluations. A comparison of the FERRET C/M ratios for each set with the average threshold reaction C/M ratio is made in Table 7-2. Note that these values are taken directly from the tables in Sections 5 and 6 and thus are based on the calculated values in the FERRET group structure which results in slightly different ratios than in Table 7-1. The use of the slightly less accurate calculated values does not affect the comparison since consistent-values are used for both the FERRET and average C/M ratios.
The comparison indicates that the FERRET flux determination is conservative in every case. On average the FERRET results are conservative by five percent in the capsules and by three percent in the cavity compared to the reaction rate average. The differences are also less than or comparable to the assigned uncertainty in every case. It is concluded that the FERRET results may be used to give a more conservative answer for the fast neutron fluence (E > 1.0 MeV) .
7-3
~~Table 7-1 Comparison of Measured and Calculated Exposure Rates from Palisades Dosi~etry Irradiations Fast Neutron Flux (E > 1.0 MeV}~~
[n/crn2-sec]
Location Calculated Measured C/M In- Vessel Dosimetry W-290 Capsule 7.36E+l0 6.71E+IO 1.10 Cycle 9 Capsule 3.77E+IO 3.52E+IO 1.07 Average 1.09 Cavity Dosimetry Cycle 8 16° l.38E+09 l.46E+09 0.95 Cycle 8 26° l.08E+09 l-.10E+09 0.98 Cycle 8 39° 7.91E+08 7.62E+08 1.04 Cycle 8-9 6° l.01E+09 9.81E+08 1.03 Cycle 9 16° 9.42E+08 8.92E+08 1.06 Cycle 9 26° 8.00E+08 7.77E+08 1.03 Cycle 9 39° 5.92E+08 5.26E+08 1.13 Average 1.03 7-4
~~Table 7-1 (Continued)~~
Comparison of Measured and Calculated Exposure Rates from Palisades Dosimetry Irradiations Fast Neutron Flux {E > 0.1 MeV2
[n/crn2-sec]
Location Calculated Measured C/M In-Vessel Dosimetry W-290 Capsule l.38E+*l l l.29E+l l 1.07 Cycle 9 Capsule 6.91E+l0 6.54E+l0 1.06 Average 1.07 Cavity Dosimetry Cycle 8 16° l.31E+l0 l.29E+l0 1.02 Cycle 8 26° 1.1 lE+lO l.02E+l0 1.09 Cycle 8 39° 9.24E+09 7.89E+09 1.17 Cycle 8-9 6° l.04E+l0 8.88E+09 1.17 Cycle 9 16° 9.10E+09 8.01E+09 1.14 Cycle 9 26° 8. l 1E+09 7.14E+09 1.14 Cycle 9 39° 6.84E+09 5.34E+09 1.28 Average 1.14 7-5
~~Table 7-1 (Continued)~~
Comparison of Measured and Calculated Exposure Rates from Palisades Do,simetry Irradiations Iron Atom Displacement Rate (dpa/s)
Location Calculated Measured C/M In- Vessel Dosimetry W-290 Capsule l.06E-IO 9.66E-11 1.10 Cycle 9 Capsule 5.36E-11 5.05E- l 1 1.06 Average 1.08 Cavity Dosimetry Cycle 8 16° 4.60E-12 4.49E-12 1.02 Cycle 8 26° 3.86E-12 3.50E-12 1.10
-I Cycle 8 39° 3.12E-12 2.66E-12 1.17 Cycle 8-9 6° 3.60E-12 3.09E-12 1.17 Cycle 9 16° 3.19E-12 2.79E-12 1.14 Cycle 9 26° 2.83E-12 2.47E-12 1.15 r Cycle 9 39° 2.29E-12 l.82E-12 1.26 I Average 1.14 7-6
~~Table 7-2 Comparison of FERRET and Reaction Rate Average C/M Ratios Fast Neutron Flux (E > 1.0 MeY)~~
Ratio Location C(M FERRET C/M Average FERRETI Average In-Vessel Dosimetry W-290 Capsule 1.10 l.15 0.96 Cycle 9 Capsule 1.08 l.14 0.95 Average 1.09 1.15 0.95 Cavity Dosimetry Cycle 8 16° 0.96 1.03 0.93 Cycle 8 26° 1.01 1.07 0.94 Cycle 8 39° 1.07 l.11 0.96 Cycle 8-9 6° 1.03 1.06 0.97 Cycle 9 16° 1.08 1.09 0.99 Cycle 9 26° 1.06 l.08 0.98 Cycle 9 39° 1.16 1.16 1.00 Average 1.05 1.09 0.97 7-7
Section 8 Best Estimate Neutron Exposure of Reactor Vessel Materials In this section the measurement results and comparisons provided in Sections 5 through 7 are combined with the results of the neutron transport calculations described in Section 4 to establish a mapping of the best estimate neutron exposure of the beltline region of the Palisades reactor vessel for Cycles 8 and 9.
In essence, an approach using analytically determined gradient information to extrapolate measurement results to locations of interest within the reactor vessel is based on the assertion that the exposure rates measured at points bracketing the reactor vessel represent the best available fast neutron flux data for the irradiation period in question and further, on the assumption that the analytically determined radial distribution functions provide accurate representations of the spatial gradients that exist among the measurement locations and points of interest within the reactor vessel wall. In addition, C/M ratios may be used for extrapolation in time to other cycles using cycle-specific transport calculations. This approach is justified to the extent that dosimetry results are consistent inside and outside the reactor vessel, and consistent for different cycles.
The results reported in this document support the application of the results in this manner for the Palisades vessel.
Using the average axial profile from Table 6-21, together with the fast neutron exposure rate data in Table 4-5 and the average C/M bias factor (l.06) as determined in Section 7, the fast neutron exposure at the reactor vessel inner radius was calculated and is tabulated in Tables 8-1 through 8-3 for fast neutron fluence (E > 1.0 MeV) and (E > 0.1 MeV), and iron atom displacements (dpa), respectively, integrated for Cycles 8 and 9. Values in these tables are based on a Cycle 8 irradiation time of 3.228 x 107 effective full power seconds (EFPS) and a Cycle 9 irradiation time of 2.579 x 107 EFPS. Values at other intermediate azimuthal angles can be determined by ratio to the Cycle 8-9 average values in Table 4-4, and values at positions through the vessel wall can be determined by using the factors in Tables 4-8, 4-11, and 4-14. The values in Tables 8-1 through 8-3 are based oh the axial profile (Table 6-21) which was averaged at each axial point.
Therefore, this distribution is not completely smooth since it still contains some structure due to statistical variation in the data. Also, since the profile is based on the reactor cavity
measurements with no fit to an axial neutron transport calculation, the change in axial profile due to transport through the reactor vessel and reactor cavity streaming has not been taken into account. These effects are relatively small in the beltline region where the maximum neutron fluence points occur, because the core height is much greater than the distance through the 8-1.
~~reactor vessel and cavity, but the flux results near the top and bottom of the core will be affected to some extent.~~
As discussed in Section 7, values of the C/M ratio at the midplane positions in the two in-vessel capsule analyses and in the Cycles 8 and 9 reactor cavity analyses are consistent within expected uncertainty. Therefore, the average C/M ratio of 1.06 was used to develop a best estimate normalization for the fluence. A detailed evaluation of the fast neutron fluence using an individual C/M bias at each azimuthal angle and for each cycle using the individual dosimetry results is not felt to be warranted since the differences in C/M ratio are not significant within uncertainty.
Using the same bias of 1.06, best estimate values of the cumulative fast neutron fluence for the Palisades reactor vessel are presented in Table 8-4. The values for Cycles 1-5 and for Cycles 6-7 are taken from previous calculations averaged over these cycles [15], as scaled by 1/1.06. Values for Cycles 8 and 9 are based on the calculations described in Section 4. Estimates for the fast neutron fluence (E > 0.1 Me V) and iron dpa can be derived from Table 8-4 using the factors in*
Table 4-5. Fast neutron fluences from Table 8-4 at 0 degrees and 30 degrees can be used to calculate the embrittlement of the longitudinal welds at these angles, and the fast neutron fluence at 16 degrees can be used to calculate the embrittlement of the circumferential weld at the maximum fluence point.
The overall uncertainties associated with the fast neutron exposure rates and integrated exposures determined for the Palisades reactor vessel stem from two basic sources; the accuracy of the neutron flux measurements at the sensor set locations and the accuracy of the radial gradient projections derived from the use of the transport theory code. Based on the least squares adjustment approach used in the FERRET analyses, the one sigma uncertainties in exposure parameters at the dosimetry locations derived from the measured reactor cavity data were approximately as follows:
1cr Uncertainty Exposure Parameter Reactor Cavity Fast Neutron Flux (E > 1.0 MeV) 8 percent Fast Neutron Flux (E > 0.1 MeV) 16-17 percent Iron Atom Displacement Rate (dpa/sec) 13-14 percent These values represent uncertainties derived from the reaction rate measurements and from the least squares fit of the output spectrum to the measured data. For the Cycle 9 in-vessel 8-2
measurements, similar uncer_tainties for the flux (E > 1.0 Me V) are obtained, but slightly lower uncertainties on the flux (E > 0.1 MeV) and iron dpa/s result from the lower relative magnitude of flux below 1.0 MeV inside the vessel.
Since the ultimate goal of the reactor cavity neutron measurement program is the evaluation of the fast neutron exposure of the reactor vessel itself, an additional uncertainty associated with the ability to translate results from the measurement locations to the points of interest within the reactor vessel must be included along with the measurement uncertainties listed above.
Information pertinent to this extrapolation uncertainty has been obtained from benchmarking studies using the Westinghouse neutron transport methodology and from several comparisons of power reactor internal surveillance capsule dosimetry and reactor cavity dosimetry for which the irradiation history of all sensors was the same [41]. Specific evaluations for the Palisades reactor vessel were made in Reference 15.
In the ,Reference 15 evaluation, it was found that the extrapolation from the in-vessel location to the reactor vessel inner radius made an uncertainty contribution of nine percent (due primarily*
to vessel radius variation and uncertainty in azimuthal shape due to uncertainty in source definition). Similarly, extrapolation from the reactor cavity to the vessel inner radius makes an uncertainty contribution of 16 percent (mainly due to cross section uncertainties for steel and to vessel wall thickness uncertainty). The total uncertainty in the reactor _vessel fluence is made up of contributions from the measurement uncertainty and the calculational uncertainty from the extrapolation from the measurement position into the vessel. Assuming that all these* uncertainty
components are independent, the overall uncertainty in the vessel fluence (derived by a com_bination of in-vessel capsule and reactor cavity measurements as defined in Section 7) is estimated to be ten percent [15]. The uncertainty in fast neutron fluence (E > 0.1 MeV) and iron dpa will be slightly higher. The latter uncertainty cannot be as precisely defined due to the need to assume uncertainties in calculated spectrum shape below 1.0 MeV since the measured reactions do not totally define the neutron flux in this energy region (as reflected in the increased uncertainty in these exposure values as determined by FERRET).
~~8-3~~
~~Table 8-1 Summary of Best Estimate Fast Neutron (E > 1.0 Mev) Exposure for the Inner Radius of the Palisades Reactor Vessel for Cycles 8 and 9~~
<jlt (E > 1.0 MeV) [n/cm 2 ]
Height Azimuthal Angle illl 0 deg 15 deg 30 deg 45 deg 8.0 8.59E+l6 l.64E+l7 8.87E+l6 6.05E+l6 7.5 l.19E+l7 2.26E+l7 l.23E+l7 8.36E+l6 7.0 l.96E+l7 3.74E+l7 2.02E+l7 l.38E+l7 6.5 2.76E+l7 5.25E+l7 2.84E+l7 l.94E+ 17 6.0 4.05E+l7 7.71E+l7 4.18E+l7 2.85E+l7 5.5 5.50E+l7 l.05E+l8 5.68E+l 7 3.88E+l7 5.0 6.87E+l7 l.31E+l8 7.09E+l7 4.84E+l7 4.5 8.15E+l7 l.55E+l8 8.41E+l 7 5.74E+l7 4.0 9.09E+l7 l.73E+l8 9.38E+l7 6.41E+l7 3.5 l.01E+l8 l.93E+l8 l.05E+l8 7.14E+l7 3.0 l.06E+l8 2.02E+l8 l.09E+l8 7.47E+l7 2.5 l. l 1E+l8 2.12E+l8 l.15E+l8 7.84E+l7 2.0 1.1lE+18 2.12E+ 18 l.15E+ 18 7.84E+l7 1.5 l.12E+l8 2.13E+l8 l.16E+l8 7.89E+l7 1.0 l.12E+ 18 2.13E+l8 l.15E+l8 7.87E+l7 0.5 l.13E+ 18 2.16E+l8 l.17E+l8 7.98E+l7 0.0 l.16E+l 8 2.22E+l8 l.20E+l8 8.19E+l7
-0.5 l. l6E+ 18 2.21E+l8 l.20E+l8 8.17E+l7
-1.0 1.14E+l8 2.17E+l8 l.18E+l8 8.03E+l7
-1.5 l.12E+l8 2.13E+l8 l.15E+ 18 7.87E+l7
-2.0 1.12E+l8 2.13E+l8 l.15E+l8 7.87E+l7
-2.5 l.07E+l8 2.04E+l8 l.l 1E+l8 7.55E+l7
-3.0 l.OOE+ 18 l.91E+l8 l.03E+l8 7.06E+l7
-3.5 9.70E+l7 l.85E+ 18 l.OOE+l8 6.84E+l7
-4.0 8.46E+l 7 1.6lE+18 8.74E+l7 5.96E+l7
-4.5 6.66E+l7 l.27E+l8 6.87E+l7 4.69E+17 Note: Height is provided relative to the axial midplane of the active core.
8-4
Table 8-2 Summary of Best Estimate Fast Neutron (E > 0.1 Mev) Exposure for the Inner Radius of the Palisades Reactor Vessel for Cycles 8 and 9
<j>t (E > 0.1 MeV) [n/cm 2 ]
Height Azimuthal Angle
@ 0 deg 15 deg 30 deg 45 deg 8.0 l.83E+l7 3.45E+ 17 l.88E+l7 l.27E+ 17 7.5 2.53E+l7 4.77E+l7 2.60E+l7 l.76E+l7 7.0 4.18E+l7 7.89E+l7 4.30E+l7 2.91E+l7 6.5 5.87E+l7 l. l lE+ 18 6.04E+l7 4.09E+l7 6.0 8.62E+l7 l.63E+l8 8.88E+l7 6.01E+l7 5.5 l.l7E+l8 2.21E+l8 l.2lE+18 8.16E+l7 5.0 l.46E+l8 2.76E+l8 l.51E+l8 l.02E+l8 4.5 l.73E+l8 3.28E+l8 l.79E+ 18 l.21E+18 4.0 l.94E+18 3.66E+l8 l.99E+18 l.35E+ 18 3.5 2.16E+l8 4.07E+l8 2.22E+l8 l.50E+l8 3.0 2.26E+l8 4.26E+l8 2.32E+l8 l.57E+l8 2.5 2.37E+l8 4.47E+l8 2.44E+l8 l.65E+l8 2.0 2.37E+l8 4.47E+l8 2.44E+l8 l.65E+l8 1.5 2.38E+l8 4.50E+l8 2.45E+l8 l.66E+l8 l.O 2.38E+l8 4.49E+l8 2.45E+l8 l.66E+l8 0.5 2.41E+l8 4.56E+l8 2.48E+l8 l.68E+l8 0.0 2.48E+l8 4.68E+l8 2.55E+l8 l.73E+l8
-0.5 2.47E+l8 4.66E+l8 2.54E+l8 l.72E+ 18
-1.0 2.43E+l8 4.58E+l8 2.50E+l8 l.69E+l8
-1.5 2.38E+l8 4.49E+l8 2.45E+l8 l.66E+l8
-2.0 2.38E+l8 4.49E+l8 2.45E+l8 l.66E+l8
-2.5 2.28E+l8 4.31E+l8 2.35E+l8 l.59E+l8
-3.0 2.13E+l8 4.03E+l8 2.20E+l8 l.49E+ 18
-3.5 2.06E+l8 3.90E+l8 2.13E+l8 l.44E+18
-4.0. l.80E+ 18 3.40E+l8 l.86E+l8 l.26E+l8
-4.5 l.42E+l8 2.68E+18 l.46E+l8 9.88E+l7 Note: Height is provided relative to the axial midplane of the active core.
8-5
~~Table 8-3 Summary of Best Estimate Iron Atom Displacements for the Inner Radius of the Palisades Reactor Vessel for Cycles 8 and 9 Iron Atom Displacements (dpa)~~
Height Azimuthal Angle
.illl 0 deg 15 deg 30 deg 45 deg 8.0 l.29E-04 2.4IE-04 l.33E-04 9. l2E-05 7.5 l.79E-04 3.33E-04 l.83E-04 l.26E-04 7.0 2.95E-04 5.50E-04 3.03E-04 2.08E-04 6.5 4.15E-04 7.73E-04 4.25E-04 2.93E-04 6.0 6.lOE-04 l.14E-03 625E-04 4.30E-04 5.5 8.28E-04 l.54E-03 8.49E-04 5.84E-04 5.0 l.03E-03 . l.93E-03 l.06E-03 7.30E-04 4.5 l.23E-03 2.29E-03 l.26E-03 8.65E-04 4.0 l.37E-03 2.55E-03 l.40E-03 9.65E-04 3.5 1.53E-03 2.84E-03 l.56E-03 l.08E-03 3.0 l.60E-03 2.97E-03 l.63E-03 l.12E-03 2.5 l.67E-03 3.12E-03 l.72E-03 l. l 8E-03 2.0 1.68E-03 3.12E-03 l.72E-03 l.18E-03 l.5 l.69E-03 3.14E-03 l.73E-03 l. l 9E-03 1.0 l.68E-03 3.13E-03 l.72E-03 l.19E-03 0.5 1.7 lE-03 3.18E-03 l.75E-03 l.20E-03 0.0 l.75E-03 3.26E-03 l.79E-03 l.23E-03
-0.5 1.75E-03 3.25E-03 l.79E-03 l.23E-03
- l.O l.72E-03 3.20E-03 l.76E-03 l.2 lE-03
-l.5 l.68E-03 3.13E-03 l.72E-03 l.19E-03
-2.0 l.68E-03 3.13E-03 l.72E-03 l.19E-03
-2.5 l.6 lE-03 3.0lE-03 l.65E-03 l.14E-03
-3.0 l.5-lE-03 2.8 lE-03 t.54E-03 l.06E-03
-3.5 l.46E-03 2.72E-03 l.50E-03 l.03E-03
-4.0 l.27E-03 2.38E-03 l.3 lE-03 8.98E-04
~~-4.5 l.OOE-03 l.87E-03 l.03E-03 7.07E-04 Note: Height is provided relative to the axial midplane of the active core.~~
~~8-6~~
~~Table 8-4 Palisades Fast Neutron F1uence (E > 1.0 MeV) Through Cycle 9 At the Reactor Vessel Clad-Base Metal Interface Cycle Cycle Cycle Cumulative~~
-Length Flux Flue nee Flue nee Cycle (EFPD) (n/cm 2 -s) (n/cm 2) (n/cm 2) 0 Degrees 379.4 4.33E+l0 1.42E+l8 l.42E+l8 2 449.l 4.33E+l0 l.68E+l8 3.10E+18
3 349.5 4.33E+l0 1.3lE+18 4.41E+l8 4 327.6 4.33E+l0 1.23E+18 5.63E+l8 5 394.6 4.33E+l0 l.48E+ 18 7. l 1E+ 18 6 333.4 4.59E+l0 l.32E+l8 8.43E+l8 7 369.9 4.59E+l0 l.47E+l8 9.90E+l8 8 373.6 2.03E+l0 6.56E+l7 l.06E+l 9 9 298.5 l.96E+l0 5.0%+17 l.l 1E+l9 16 Degrees 379.4 5.69E+l0 l.86E+l8 l.86E+ 18 2 449.l 5.69E+l0 2.21E+l8 4.07E+l8 3 349.5 5.69E+l0 l.72E+ 18 5.79E+l8 4 327.6 5.69E+l0 l.61E+l8 7.40E+ 18 5 394.6 5.69E+l0 1.94E+l8 9.34E+l8 6 333.4 5.90E+l0 l.70E+l8 l.lOE+ 19 7 369.9 5.90E+l0 l.88E+l8 l.29E+l9 8 373.6 4.61E+l0 1.49E+l8 l.44E+l9 9 298.5 2.89E+l0 7.45E+l7 l.52E+ 19 8-7
I
~~Table 8-4 (Continued)~~
Palisades Fast Neutron Fluence (E > 1.0 Me V) Through Cycle 9 At the Reactor Vessel Clad-Base Metal Interface Cycle Cycle Cycle Cumulative Length Flux Fluence Fluence Cycle (EFPD) (n/cm 2-s) (n/cm 2) (n/cm 2) 30 Degrees 379.4 4.43E+ 10 1.45E+l8 l.45E+l8 2 449.1 4.43E+l0 1.72E+l8 3.17E+l8 3 349.5 4.43E+l0 l.34E+l8 4.51E+l8 4 327.6 4.43E+10 1.26E+l8 5.77E+l8 5 394.6 4.43E+l0 l.5IE+l8 7.28E+l8 6 333.4 4.52E+l0 l.30E+ 18 8.58E+l8 7 369.9 4.52E+l0 1.44E+l8 l.OOE+l9 8 373.6 2.21E+10 7.13E+l7 l.07E+l9 9 298.5 l.89E+10 4.87E+l7 l.12E+l9 45 Degrees 379.4 2.81E+10 9.22E+l7 9.22E+l7 2 449.l 2.81E+10 1.09E+ 18 2.01E+l8 3 349.5 2.81E+10 8.49E+17 2.86E+l8 4 327.6 2.81E+10 7.96E+l7 3.66E+l8 5 394.6 2.81E+10 9.58E+l7 4.62E+l8 6 333.4 2.86E+10 8.23E+l7 5.44E+l8 7 369.9 2.86E+10 9.14E+l7 6.35E+l8 8 373.6 l.67E+10 5.39E+l7 6.89E+l8 9 298.5 l.09E+10 2.80E+l7 7.17E+l8 8-8
Section 9 Summary and Conclusions This report has presented the results of the successful reactor cavity neutron dosimetry measurements carried out during Palisades Fuel Cycles 8 and 9 and the Cycle 9 in-vessel dosimetry capsule measurements. The measurements established a basis for validation of calculated reactor vessel fast neutron exposures at key points and together with the calculations provided data for evaluation of fast neutron exposures at all points within the Palisades reactor vessel for these cycles.
Both Cycles 8 and 9 in Palisades were unique cycles designed to significantly lower the reactor vessel exposure at key points. The reactor cavity dosimetry measurements for these cycles show that the calculated- flux reductions are predicted accurately and confirm the success of the fuel management. Combined with the previous Cycle 1-5 W-290 surveillance capsule measurement, confidence is gained that the calculations are able to track changes in reactor vessel fast neutron exposure due to the changing core loading patterns, as indicated by the consistency of the results.
In addition, the simultaneous irradiation in Cycle 9 of the in-vessel and ex-vessel dosimetry provides a unique validation of the neutron transport calculation through the vessel wall. The simultaneous measurement eliminates uncertainty due to differences in irradiation conditions, and the agreement between the in- and ex-vessel measurements supports the adequacy of the calculational methodology and the cross section sets employed. This result is consistent with the conclusions drawn in Reference 41.
Based on the comparisons of measurement results with calculations tabulated in Section 6, it is concluded that the DOT calculations are conservative and overpredict the reactor vessel fast neutron fluence (E > 1.0 MeV) by six percent (based on the average of the in-vessel and reactor cavity calculations). Using this bias, best estimate values of reactor vessel fast neutron exposure for Cycles 8 and 9 were calculated and are presented in Tables 8-1 through 8-3.
It should be rioted that, in contrast to the Palisades Plant results, the general trend in other PWR plants with reactor cavity neutron dosimetry behind thermal shields or neutron pads is for the measurements to exceed the calculated values. Typical biases are about 12 percent. In cases
where the additional shielding is not present, as in Palisades, this bias seems to disappear. While the cause of this phenomenon is not known at this time, it is probably due to a combination of errors in cross section data and calculational methods, and further work needs to be done to gain understanding. However, since the Palisades dosimetry measurements cover multiple cycles and 9-1
~~include data both from inside and outside the reactor vessel, there is high confidence in the tabulated results for the vessel exposure based on these measurements.~~
For Palisades Plant, the most limiting reactor vessel fast neutron exposure is to the circumferential beltline weld which has the peak fluence at angles symmetric with 16 degrees.
The exposure to the longitudinal welds at 0 degrees and 30 degrees is also important. At all these angles, the extensive dosimetry data from both the Cycle 8 and Cycle 9 reactor cavity neutron dosimetry, together with the d_ata from the in-vessel capsules, support the conclusion that the present calculational evaluation of fast neutron exposure is conservative. Best estimate exposures for these welds are given in Section 8 using the measured bias of 1.06 to correct the calculated values. The best estimate maximum fast neutron fluence (E > 1.0 Me V) at the end of Cycle 9 is l.52x 10 19 n/cm2 for the circumferential weld, 1.11x10 19 n/cm 2 for the longitudinal weld at 0 degrees, and l. l 2x 10 19 n/cm 2 for the longitudinal weld at 30 degrees. The uncertainty in these values is estimated to be +/-10 percent.
Continuation of the reactor vessel monitoring program will provide further data to improve the*
characterization of the neutron environment in the vessel and to record the effects of changing fuel cycles. This will enable the uncertainty in projection of the reactor vessel exposure to be reduced by basing the projections on realistic exposure levels with known uncertainties .
9-2
Section 10 References
~~1. Fero, A. H., "Reactor Cavity Neutron Measurement Program for Consumers Power Company Palisades Nuclear Plant," WCAP-11911, December 1988.~~
2. Fero, . A. H., "Reactor Cavity Neutron Measurement Program for Consumers Power Company Palisades Nuclear Plant," WCAP-12847, January 1991. *
~~3. Lippincott, E. P. and McElroy; W. N., "Power Reactor Benchmark Studies", Reactor Dosimetry: Methods, Applications, and Standardization, ASTM STP 1001, 1989, pp 308-313.~~
~~4. McElroy, W. N., Ed., "LWR-PV-SDIP: PCA Experiments and Blind Test,"~~
~~NUREG/CR-1861, 1981.~~
~~5. Fero, A. H., "Neutron and Gamma-Ray Flux Calculations for the VENUS PWR Engineering Mockup," WCAP-i 1173, NUREG/CR-4827, January 1987.~~
~~6. Lippincott, E. P., et. al., "Evaluation of Surveillance Capsule and Reactor Cavity Dosimetry from H. B. Robinson Unit 2, Cycle 9," WCAP-11104; NUREG/CR-4576, February 1987. .~~
7.. Lippincott, E. P., Anderson, S. L., and Fero, A.H., "Application of Ex-Vessel Neutron Dosimetry for Determination of Vessel Fluence", Reactor Dosimetry: Methods, Applications, and Standardization, ASTM STP 1001, 1989, pp 147-154.
8. Lippincott, E. P. and Anderson, S. L., "Reactor Vessel Fluence Monitoring and Reduction", Proceedings of the Seventh ASTM-Euratom Symposium on Reactor Dosimetry, Strasbourg, France, 27-31 August 1990, p. 153-160, Kluwer Acaderriic Publishers, 1992.
9. ASTM Designation E853-87, "Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results," in ASTM Standards, Section 12, American Society for Testing and Materials, Philadelphia, Pa., 1992.
~~10-1~~
10. ASTM Designation B693-79, "Standard Practice for Characterizing Neutron Exposures in Ferritic Steels in Terms of Displacements per Atom (DPA), E706(ID)," in ASTM Standards, Section 12, American Society for Testing and Materials, Philadelphia, Pa.,
~~1992.~~
~~11. ABB/CE Report No. 98086-MCC-002, Revision 2, "Summary Report on Manufacture of Palisades In-Vessel Dosimetry Capsule -Assembly," January 1992 .~~
12. Soltesz, R . G. , et.. al., "Nuclear Rocket Shielding Methods, Modification, Updating, and Input Data Preparation - Volume 5 - Two Dimensional Discrete Ordinates Transport Technique," WANL-PR-(LL)-034, August 1970 .
~~13.. SAILOR RSIC DATA LIBRARY COLLECTION DLC-76, "Coupled Self-Shielded, 47 Neutron, 20 Gamma Ray, P3, Cross Section Library for Light Water Reactors.~~
14. Lippincott, E.P., and Fero, A..H . , "Reactor Cavity Neutron Measurement Program for*
~~Consumers Power Company Palisades Nuclear Plant", WCAP-13042, December 1991.~~
~~15 . Lippincott, E.P., "Consumers Power Comp;my Palisades Nuclear Plant Reactor Vessel Fluence Analysis", WCAP-13348, May 1992.~~
~~16. Jolly, 0. P., "Pin Power Data Base for Cycle 8", from EA-P-PTS-90-017 (1990),~~
transmitted by letter December 14, 1990.
-17.. Ho, John C., "DOT Neutron Source Database for Cycle 9 Operation", transmitted by letter July 7, 1992.
~~18. Shields, K. J., "Palisades Core Geometry Parameter List", EA-PTS-87-004 (1987),~~
~~transmitted by FAX November 2, 1990.~~
19. ASTM Designation E706-87, "Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards," in ASTM Standards, Section 12, American Society for Testing and Materials, Philadelphia, Pa., 1992.
~~20. ASTM Designation E261-90, "Standard Practice for Determining Neutron Fluence Rate, Fluence, and Spectra by Radioactivation Techniques," in ASTM Standards, Section 12,~~
~~American Society for Testing and Materials, Philadelphia, Pa. 1992.~~
~~10-2~~
21. ASTM Designation E262-86, "Standard Method for Measuring Thermal Neutron Reaction and Fluence Rates by Radioactivation Techniques." in ASTM Standards, Section 12, American Society for Testing and Materials, Philadelphia, Pa. 1992.
22. ASTM Designation E263-88, "Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Iron," in ASTM Standards, Section 12, American Society for Testing and Materials, Philadelphia, Pa., 1992.
23. ASTM Designation E264-87, "Standard Test Method for Measuring Fast-Neutron Reaction Rates by ~adioactivation of Nickel," in ASTM Standards, Section 12, Ameiican Society for Testing and Materials, Philadelphia, Pa., 1992.
24. ASTM Designation E481-86, "Standard Test Method for Measuring Neutron Fluence Rate by Radioactivatiori of Cobalt and Silver," in ASTM Standards, Section 12, American Society for Testing and Materials, Philadelphia, Pa., 1992 .
25. ASTM Designation E523-87, "Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Copper," in ASTM Standards, Section 12, American Society for Testing and Materials, Philadelphia, Pa., 1992.
26. ASTM Designation E526-87, "Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Titanium", in ASTM Standards, Section 12, American Society for Testing and Materials, Philadelphia, PA, 1992.
27. ASTM Designation E704-89, "Standard Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238," in ASTM Standards, Section 12, American Society for Testing and Materials, Philadelphia, Pa., 1992 ..
~~28. ASTM Designation E705-89, "Standard Test Method for Measuring Reaction Rates by~~
~~Radioactivation of Neptunium-237," in ASTM Standards, Section 12, American Society for Testing and Materials, Philadelphia, Pa., 1992.~~
~~29 . ASTM Designation El005-84, "Standard Method for Application and Analysis of.~~
~~Radiometric Monitors for Reactor Vessel Surveillance," in ASTM Standards, Section 12, American Society for Testing and Materials, Philadelphia, Pa., 1992.~~
~~10-3~~
30. ASTM Designation E1297-89, "Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium," in ASTM Standards, Section 12, American Society for Testing and Materials, Philadelphia, Pa., 1992.
~~31. Jolly, 0. P., "Power History Data for Cycle 8 Operation" from EA-P-PTS-90-016, 1990, transmitted by letter November 14, 1990.~~
~~32. Jolly, 0. P., "Power History Data for Cycle 9" transmitted by letter March 11, 1992.~~
33. Schmittroth, E. A., "FERRET Data Analysis Code", HEDL-TME-79-40, Hanford Engineering Development Laboratory, Richland, Washington, September 1979. *
34. McElroy, W. N., et. al., "A Computer-Automated Iterative Method of Neutron Flux Spectra Determined by Foil Activation," AFWL-TR-67-41, Volumes I-IV, Air Force Weapons Laboratory, Kirkland AFB, NM, July 1967.
~~35 . Maerker, R. E. as reported by Stallman, F. W., "Workshop on Adjustment Codes and~~
~~36.~~
Uncertainties - Proc. of the 4th ASTM/EURATOM Symposium on Reactor Dosimetry,"
NUREG/CP-0029, NRC, Washington, D.C., July 1982.
ASTM Designation E482-89, "Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance", in ASTM Standards, Section 12, American Society for Testing and Materials, Philadelphia, PA, 1992.
37. ASTM Designation E560-84, "Standard Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results", in ASTM Standards, Section 12, American Society for Testing and Materials, Philadelphia, PA, 1992.
38. ASTM Designation E844-86, "Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance", in ASTM Standards, Section 12, American Society for Testing and M~terials, Philadelphia, PA, 1992.
39. ASTM Designation E944-89, "Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance", in ASTM Standards, Section 12, American Society for Testing and Materials, Philadelphia, PA, 1992.
~~10-4~~
~~40. Fero, A. H., "Reactor Cavity Neutron Measurement Program for Consumers Power Company Palisades Nuclear Plant (As-Installed Description for Cycle 10)," WCAP-13552, November 1992.~~
~~41. Anderson, S. L., "Westinghouse Fast Neutron Exposure Methodology for Pressure Vessel Fluence Determination and Dosimetry Evaluation", WCAP-13362, May 1992. [Proprietary Class 2]~~
10-5
Appendix A Irradiation History and Measured Specific Activities In this appendix, the irradiation history for the Palisades Plant during Cycle 8 [31] and Cycle 9
[32] and the measured specific activities of radiometric sensors irradiated in the reactor cavity during Cycles 8 and 9 are provided. The Cycle 8 measurements have been decay corrected to an arbitrary reference date of December 12, 1990 and the Cycle 9 measurements to March ..+.
1992.
The irradiation history of Cycle 8 is given in Table A-1 and that for Cycle 9 in Table A-2.
The irradiation capsule loading diagram and the measured specific activities of the radiometric monitors from the Cycle 8 irradiation are provided in Tables A-3, A-5 and A-6. For the multiple foil sensor sets, the individual foil ID can be correlated with the capsule loading diagrams provided and the capsule locations in Section 6 to determine the location of the foil within the reactor cavity during irradiation.
The irradiation capsule loading diagram and the measured specific activities of the radiometric monitors from the Cycle 9 irradiation are provided in Tables A-4, A-7 and A..,8. For the multiple foil sensor sets, the individual foil ID can be correlated with the capsule loading diagrams provided and the capsule locations in Section 6 to determine the location of the foil within the reactor cavity during irradiation.
The measured specific activities for the dosimeters contained in the in-vessel dosimetry capsule irradiated during Cycle 9 at the W-290 position are provided in Table A-9. Photographs of these dosimeters prior to removing the grooved stainless steel sheaths are in Figures A-1 through A-3 .
A-1
Table A-1 Palisades Cycle 8 Thermal Power Generation Month MW-hr Startup/Shutdown Dates l l/88 29640 Cycle 8 Startup: November l, 1988 12/88 454344 1/89 1657920 2/89 0 3/89 1248144 4/89 1392120 5/89 1499736 6/89 1457664 7/89 1510872 8/89 1341864 9/89 1453344 10/89 504 l l/89 0 12/89 502200 l/90 1372848 2/90 1352352 3/90 1378920 4/90 741096 5/90 *536208 6/90 1047984 7/90 1501584 8/90 1501896 9/90 704184 Cycle 8 Shutdown: September 15. 1990 Total: 22,685,424 MW-hr (3.228x 107 EFPS)
Reference Thennal Power: 2530 MWt A-2
Table A-2 Palisades Cycle 9 Thermal Power Generation Mo 11th MW-hr Startup/Shutdown Dates 3/91 480456 Cycle 9 Startup: March 10, 1991 4/91 1809167 5/91 1885464 6/91 1818648 7/91 1143408 8/91 1837560 9/91 1818984 10/91 1882521 11/91 1712592 12/91 1513368 1/92 1867224 2/92 357888 Cycle 9 Shutdown:
~~February 6, 1992 Total: 18,127,280 MW-hr (2.579x 107 EFPS)~~
Reference Thennal Power: 2530 MWt A-3
Radiometric Monitor Foil ID Capsule ID Bare or and Cadmium U-238 U-238 NBS Position Shielded Fe Ni Cu Ti Nb Co (nat) (dep) PUD Np-237 A-1 B A - - - - A - - - - OQ A-2 A-3 Cd Cd K
A BA AK BA K
~~AA BG l INI 8~~
-*3 3 0
en (1)
~~i en~~
~
(1)
(i" "'1
"'1 . en B-1 B B - - - - B - . - - - (') "O B-2 Cd L B BB AL BB L AB BH - - P:l 0
'O ::E B-3 Cd - - - - - - - - 12N2 9 en
~
(1)
"'1
~ (')
C-1 B c - - - - c - - - - (') 0 ....,
C-2 Cd M c BC AM BC M AC BI - - 0
~~i 'O 3 P:l CT~~
> I C-3 Cd - - - - - - - - 13N3 IO ...... P:l (1) ::i ~
.j:::..
aen '< >
D-1 B D - - - - D - - - -
s~
I I.,,.)
D-2 Cd . N D BD AN BO N AD BJ - -
en en -*
D-3 Cd - - - - - - - - 14N4 11
=
P:l P:l O..*
(1) (1) 0.. en E-1 B E - - - - E - - - -
E-2 Cd 0 E BE AO BE 0 AE AL - - 8'
"'1 z
~
(")
E-3 Cd - - - - - - - - 15N5 12 (') ~
(')
P:l
"'1 F-1 F-2 F-3 B
Cd Cd F
p F
BF AP BF F
p AF AM 16N6**
13
~ "O
~~'XJ P:l-~~
~~i G-1 B G - - - - G - - - -~~
G-2 Cd. R G BG AR BG R AG u - -
G-3 Cd -- - - - - - - - 17N7 14
Radiometric Monitor Foil ID ob1 0 ::l Vl Vl Capsule Bare or .... i::
3 3(1)
ID and Cadmium .U-238 U-238 (1)
~'"I Position Shielded Fe Ni Cu Ti Nb
~~Co (nat) (dep) Np-237 '"I Vl n""d Ill 0 J-1 B c - - - - 0 - - - "C Vl i::~~
~
(1)
'"I J-2 Cd M 0 AO BE AC AO - - - Ci" (")
J-3 Cd - - - - - - c c 16 no3 0
~
pJ
~~l "C er I K-1 B D - - - - p - - . -~~
~~(1) pJ~~
~~l Ci" VI p g '< )>~~
K-2 Cd N AP BF AD AP - - - Vl ""d I
+:>- .
K-3 Cd - - - - - - *D D 17 5' Vl e.
...... Vl pJ Ill L-1 B E - - ~
- R - - - ~
o.
g-Vl L-2 Cd 0 R AR BG AE AR - - - ....,z L-3 Cd - - - - - - E .. E. 18 O
'"I
. i::
()
(") .......
'< (1)
N-1 B G - - - - T - - - () ~
Ci" ""d N-2 Cd R T AT BI AG AT - - -
N-3 Cd - - - - - - G u 20 '° ......§
Table A-5
~~Foil ID Palisades Cycle 8 Reactor Cavity Dosimetry Set Results Lab Sample#~~
Dosimeter Material Nuclide dps/rng B 90-1857 Fe Mn-54 1.74E+Ol L 90-1858 Fe Mn-54 1.72E+O I D 90-1870 Fe Mn-54 l.32E+O.I N 90-1871 Fe Mn-54 l.30E+OI E 90-1883 Fe Mn-54 4.28E+OO 0 90-1884 Fe Mn-54 3.89E+OO G 90-1896. Fe Mn-54 9.36E+OO R 90-1897 Fe Mn-54 9.35E+OO B 90-1859 Ni Co-58 2.01E+02 D 90-1872 Ni Co-58 l.51E+02 E 90-1885 Ni Co-58 4.97E+Ol G 90-1898 Ni Co-58 l.07E+02 BB 90-1860 Cu Co-60 7.45E-O 1 BD 90-1873 Cu Co-60 5.73E-Ol BE 90-1886 Cu Co-60 l.52E-Ol BG 90-1899 Cu Co-60 4.22E-01 AL 90-1861 Ti Sc-46 4.57E+OO AN 90-1874 Ti Sc-46 3.50E+OO AO 90-1887 Ti Sc-46 l.05E+OO AR 90-1900 Ti Sc-46 2.48E+OO B 90-1863 Al Co Co-60 2.71E+02 L 90-1864 Al Co Co-60 l.80E+02 D 90-1876 Al Co Co-60 2.53E+02 N 90-1877 Al Co Co-60 1.75E+02 E 90-1889 Al Co Co-60 l.52E+02 0 90-1890 Al Co Co-60 l.02E+02 G 90-1902 Al Co Co-60 2.81E+02 R 90-1903 Al Co Co-60 l.70E+02
~~dps /(mg of dosimeter material) on Dec. 12, 1990.~~
A-6
Table A-5 (Continued)
Palisades Cycle 8 Reactor Cavity Dosimetry Set Results Lab Dosimeter Foil ID Sample# Material Nuclide dps/mg AB 90-1865 U(l) Zr-95 4.16E+Ol BH 90-1866 U(l) Zr-95 l.24E+O l 12 90-1867 U(2) Zr-95 1.22E+O I N2 90-1868 U(l) Zr-95 4.02E+Ol AD 90-1878 U(l) Zr-95 3.67E+Ol BJ 90-1879 U(l) Zr-95 9.75E+OO 14 90-1880 U(2) Zr-95 9.75E+OO N4 90-1881 U(l) Zr-95 3.66E+Ol AE 90-1891 U(l) Zr-95 ********
AL 90-1892 U(l) Zr-95 3.78E+OO 15 90-1893 U(2) Zr-95 3.22E+OO N5 90-1894 U(l) Zr-95 l.90E+Ol AG 90-1904 U(l) Zr-95 3.44E+Ol u 90-1905 U(l) Zr-95 7.48E+OO 17 90-1906 U(2) Zr-95 6.19E+OO N7 90-1907 U(l) Zr-95 3.59E+Ol AB 90-1865 U(l) Ru-103 l.75E+Ol BH 90-1866 U(l) Ru-103 8.64E+OO 12 90-1867 U(2) Ru-103 8.88E+OO N2 90-1868 U(l) Ru-103 l.69E+Ol AD 90-1878 U(l) Ru-103 l.48E+Ol BJ 90-1879 U(l) Ru-103 6.78E+OO 14 90-1880 U(2) Ru-103 6.95E+OO N4 90-1881 U(l) Ru-103 l .48E+O I AE 90-1891 U(l) Ru-103 ********
AL 90-1892 U(l) Ru-103 2.46E+OO 15 90-1893 U(2) Ru-103 2.29E+OO N5 90-1894 U(l) Ru-103 6.97E+OO AG 90-1904 U(l) Ru-103 l.30E+Ol u 90-1905 U(l) Ru-103 4.86E+OO 17 90-1906 U(2) Ru-103 4.39E+OO N7 90-1907 U(l) Ru-103 l.35E+Ol
~~dps I (mg of dosimeter material) on Dec. 12, 1990.~~
A-7
Table A-5 (Continued)
Palisades Cycle 8 Reactor Cavity Dosimetry Set Results Lab Dosimeter Foil ID Sample# Material Nuclide dps/mg AB 90-1865 U(l) Cs-137 3.70E+OO BH 90-1866 U(l) Cs-137 l.30E+OO 12 90-1867 U(2) Cs-137 l.27E+OO N2 90-1868 U(l) Cs-137 3.57E+OO AD 90-1878 U(l) Cs-137 3.24E+OO BJ 90-1879 U(l) Cs-137 9.75E-Ol 14 90-1880 U(2) Cs-137 9.8 lE-Ol N4 90-1881 U(l) Cs-137 3. l9E+OO AE 90-1891 U(l) Cs-137 ********
AL 90-1892 U(l) Cs-137 3.46E-O l 15 90-1893 U(2) Cs-137 3.03E-O 1 N5 90-1894 U(l) Cs-137 *l.54E+OO AG 90-1904 U(l) Cs-137 2.98E+OO u 90-1905 U(l) Cs-137 7.64E-Ol 17 90-1906 U(2) Cs-137 6.5 lE-01 N7 90-1907 U(l) Cs-137 3.1 IE+OO 9 90-1869 Np-237 Zr-95 2.39E+02 11 90-1882 Np-237 Zr-95 l.75E+02 12 90-1895 Np-237 Zr-95 6.03E+Ol 14 90-1908 Np-237 Zr-95 l.30E+02 9 90-1869 Np-237 Ru-103 l.44E+02 11 90-1882 Np-237 Ru-103 l.06E+02 12 90-1895 Np-237 Ru-103 3.95E+Ol 14 90-1908 Np-237 Ru-103 7.98E+Ol 9 90-1869 Np-237 Cs-137 2.40E+Ol 11 90-1882 Np-237 Cs-137 'l.80E+Ol 12 90~1895 Np-237 Cs-137 , 5.94E+OO 14 90-1908 Np-237 Cs-137 l.28E+Ol
~~dps I (mg of dosimeter material) on Dec. 12, 1990.~~
~~A-8~~
~~(This page intentionally left blank.)~~
A-9
Table A-6
~~Palisades Cycle 8 Reactor Cavity Gradient Chain Measurements Reference Azimuth: 280 deg.~~
Bead Chain Tag ID: 280 Chain Composition Fe: 0.706 Ni: 0.0881 Co: 0.00176 Feet [<----------- dps/mg of chain @ 12/12/90 ----------->]
from Lab - Mn - Co - Co-6ll -
Mid plane Sample# dps/mg dps/mg ups/mg
+0.5 90-l 915A l.14E+Ol l.92E+Ol l.01E+02 0.0
-0.5 90-19158 l.16E+Ol l.99E+O l 1.01E+02
-1.0 90-1915C l.16E+Ol l.88E+Ol l.01E+02
-1.5 90-19150 l.13E+Ol l.79E+Ol 9.90E+Ol
-2.0 90-1915E l.09E+Ol l.73E+Ol 9.62E+Ol
-2.5 90-1915F 9.19E+OO l.72E+Ol 9.34E+Ol
-3.0 90-1915G 8.84E+OO l.49E+Ol 8.95E+Ol
-3.5 90-1915H 8.44E+OO l.43E+Ol 8.63E+Ol
-4.0 90-19151 6.17E+OO l.19E+Ol 8.07E+Ol
-4.5 90-19151 5.lOE+OO 8.90E+OO 6.87E+Ol
-5.0 90-1915K 3.43E+OO 5.92E+OO 5.86E+Ol
-5.5 90-l 915L 2.27E+OO 4.24E+OO 5.39E+O l A-10
Table A-6 (Continued)
Palisades Cycle 8 Reactor Cavity Gradient Chain Measurements Reference Azimuth: 290 deg.
Bead Chain Tag ID: 290 Chain Composition Fe: 0.683 Ni: 0.092 Co: 0.00174 Feet [<----------- dps/mg of chain @ 12/ 12/90 -------- ---> l from Lab - Mn - Co - Co Midplane Sample# dps/mg dps/mg dps/mg
+0.5 90-l916A 8.36E+OO 1.45E+Ol 9.08E+O l 0.0
-0.5 90-19168 8.52E+OO l.40E+Ol 9.06E+Ol
-1.0 90-l 9 l6C 8.68E+OO l.4lE+Ol 9.09E+Ol
-1.5 90-19160 8.52E+OO l.46E+Ol 8.96E+Ol
-2.0 90-19 l6E 8.32E+OO l.45E+Ol 8.90E+Ol
-2.5 90-l9 l6F 7.84E+OO l.39E+Ol 8.57E+Ol
~~-3.0~~
-3.5
-4.0
-4.5
-5.0 90-19160 90-1916H 90-19161 90-19161 90-1916K 7.46E+OO 7.26E+OO 6.l5E+OO 5.17E+OO 3.45E+OO l.28E+Ol l.22E+Ol l.15E+Ol 8.91E+OO 5.99E+OO 8.49E+Ol 8.l6E+Ol 7.72E+Ol 7.23E+Ol 5.79E+Ol A-11
Table A-6 (Continued)
Palisades CyCle 8 Reactor Cavity Gradient Chain Measurements Reference Azimuth: 315 deg.
Bead Chain Tag ID: 315 Chain Composition Fe: 0.673 Ni: 0.0868 Co: 0.00164 Feet [<----------- dps/mg of chain @ 12/ l 2/90 ----------->]
from Lab - Mn - Co - Co Mid plane Sample# dps/mg dps/mg Jps/rng
+0.5 90-l 9 l8A 6.19E+OO l.06E+Ol l .02E+Cl2 0.0
-0:5 90-1918B 6.07E+OO 9.43E+OO l.03E+02
-1.0 90-l918C 6.07E+OO 9. l2E+OO l.OlE+02
-1.5 90-19180 5.42E+OO 9.61E+OO l.01E+02
-2.0 90-1918E 5.7lE+OO 9.42E+OO 9.8lE+O1
-2.5 90-1918F 5.03E+OO 8.21E+OO 9.54E+Ol
-3.0 90-l918G 4.93E+OO 8.23E+OO 8.91E+Ol
-3.5 90-1918H 4.40E+OO 7.49E+OO 8.66E+Ol
-4.0 90-19181 3.84E+OO 7.13E+OO 7.92E+U 1
-4.5 90-19181 3.53E+OO 5.94E+OO 7.38E+Ol
-5.0 90-1918K 2.50E+OO 4.44E+OO 5.92E+Ol
-5.5 90-1918L l.85E+OO 3.64E+OO 5.02E+Ol A-12
Table A-6 (Continued)
~~Palisades Cycle 8 Reactor Cavity Gradient Chain Measurements Reference Azimuth: 330 deg.~~
Bead Chain Tag ID: 330 Chain Composition Fe: 0.687 Ni: 0.0935 Co: 0.00164 Feet [<----------- dps/mg of chain @ 12/ 12/90 -----------> l from Lab - Mn - Co - Co Mid plane Sample# dps/mg dps/mg dps/mg
+0.5 90-1919A 8.69E+OO l.51E+Ol l .14E+U2 0.0 90-19198 9.69E+OO l.44E+Ol l .14E+02
-0.5 90-1919C 9.19E+OO l.56E+Ol l.14E+02
-1.0 90-19190 9.32E+OO l.48E+Ol l. l 1E+02
-1.5 90-1919E 8.24E+OO l.39E+Ol l.09E+02
-2.0 90-l 9 l 9F 7.85E+OO l.43E+Ol l.05E+02
-2.5 90-1919G 7.34E+OO l.30E+Ol 9.96E+Ol
-3.0 90-l 919H 6.68E+OO l.l6E+Ol
~~9.38E+Ol~~
-3.5 90-19191 5.52E+OO 9.69E+OO 8.75E+Ol
-4.0 90-19191 4.74E+OO 8.09E+OO 8.03E+OI
-4.5 90-1919K 3.37E+OO 5.40E+OO 6.45E+OI
-5.0 90-1919L 2.44E+OO 4.30E+OO 5.52E+Ol
-5.5 90-1919M l.46E+OO 3.12E+OO 5.08E+O I A-13
Table A-6 (Continued)
Palisades Cycle 8 Reactor Cavity Gradient Chain Measurements Reference Azimuth: 30 deg.
Bead Chain Tag ID: 30 Chain Composition Fe: 0.644 Ni: 0.0874 Co: 0.00126 Feet [<----------- dps/mg of chain @ 12112/90 ----------->I from Lab - Mn - Co - Co Midplane Sample# dps/mg dps/mg dps/mg
+8.0 90-l 909A 4.32E-Ol 9.65E-Ol 3.05E+O I
+7.5 90-19098 5.75E-01 l.09E+OO 3.31E+Ol
+7.0 90-1909C 1.1 lE+OO l.94E+OO 3.92E+Ol
+6.5 90-19090 l.38E+OO 2.40E+OO 4.06E+Ol
+6.0 90-1909E 2.33E+OO 3.92E+OO 4.65E+OI
+5.5 90-1909F 2.94E+OO 5.56E+OO 4.77E+Ol
+5.0 90-19090 3.81E+OO 6.61E+OO 5.50E+Ol
+4.5 90-1909H 4.72E+OO 8.38E+OO 5.90E+Ol
+4.0 90-19091 5.04E+OO 8.84E+OO 5.85E+Ol
+3.5 90-19091 5.98E+OO 1.02E+Ol 6.53E+Ol
+3.0 90-1909K 6.28E+OO l.05E+Ol 6.80E+Ol
+2.5 90-1909L 6.64E+OO 1.06E+Ol 6.97E+Ol
+2.0 90-1909M 6.57E+OO l.04E+Ol 7.36E+Ol
+l.5 90-1909N 6.46E+OO l.07E+Ol 7.58E+Ol
+1.0 90-19090 6.59E+OO 1.12E+Ol 7.6 lE+O l
+0.5 90-1909P 6.77E+OO l.09E+Ol 7.93E+Ol 0.0 90-1909Q 6.89E+OO l.12E+Ol 8.02E+Ol
-0.5 90-1909R 6.84E+OO l.14E+Ol 7.94E+Ol
-1.0 90-1909S 6.90E+OO l.14E+Ol 8.18E+Ol
-1.5 90-1909T 6.50E+OO l.24E+Ol 7.93E+Ol
-2.0 90-1909U 6.93E+OO l.17E+Ol 7.98E+OI
-2.5 90-1909V 6.64E+OO l.18E+Ol 7;83E+O l
-3.0 90-1909W 6.33E+OO l.lOE+Ol 7.40E+Ol
-3.5 90-1909X 6.06E+OO 9.96E+OO 7.17E+Ol
-4.0 90-1909Y 5.47E+OO 9.27E+OO 6.70E+Ol
-4.5 90-1909Z 4.38E+OO 8.24E+OO 5.98E+Ol A-14
Table A-6 (Continued)
Palisades Cycle 8 Reactor Cavity Gradient Chain Measurements Reference Azimuth: 90 deg.
Bead Chain Tag ID: 90 Chain Composition Fe: 0.677 Ni: 0.091 Co: (J.lJ()J 87 Feet [<----------- dps/mg of chain @ l2/l2/90 ----------->]
from Lab - Mn - Co - Co Midplane Sample# dps/mg dps/mg dps/mg
+8.0 90-19lOA 6.42E-Ol l.20E+OO 4.55E+OI
+7.5 90-19108 8.34E-Ol l.65E+OO 4.99E+OI
+7.0 90-19 lOC l.39E+OO 2.98E+OO 5.93E+Ol
+6.5 90-19 lOD 2.lOE+OO 3.83E+OO 6.38E+OI
+6.0 90-19 lOE 3.12E+OO 5.18E+OO 7.13E+Ol
+5.5 90-19 lOF 3.90E+OO 6.85E+OO 7.62E+Ol
+5.0 90-1910G 4.74E+OO 8.35E+OO 8.65E+Ol
+4.5 90-19 lOH 5.74E+OO 9.69E+OO 9. l8E+Ol
+4.0 90-l9lOI 6.32E+OO l.07E+Ol 9.63E+Ol
+3.5 90-19 lOJ 6.97E+OO l.26E+Ol l.05E+02
+3.0 90-19 lOK 7.25E+OO l.30E+Ol l.08E+02
+2.5 90-19 lOL 7.52E+OO 1.3 !E+Ol 1.17E+02
+2.0 90-19lOM 7.65E+OO l.42E+Ol l.26E+02
+1.5 90-1910N 7.44E+OO l.26E+Ol l.18E+02
+l.O 90-19100 7.15E+OO l.36E+Ol 1.30E+02
+0.5 90-1910P 7.55E+OO 1.3 lE+Ol l.28E+02 0.0 90-1910Q 8.43E+OO l.25E+Ol l.32E+02
-0.5 90-19 lOR 7.96E+OO l.30E+Ol l.34E+02
-1.0 90-1910S 7.24E+OO l.27E+Ol l.32E+02
-1.5 90-19lOT 7.33E+OO 1.18E+Ol l.31E+02
-2.0 90-1910U 7.02E+OO l.20E+Ol l.27E+02
-2.5. 90-1910V 7.04E+OO l.26E+Ol l.22E+02 *
-3.0 90-19lOW 6.0!E+OO l.13E+Ol l.l3E+02
-3.5 90-1910X 6.64E+OO 1.07E+Ol l.09E+02
-4.0 90-19 lOY 5.58E+OO 8.90E+OO 9.91E+Ol
-4.5 90-19 lOZ 4.57E+OO 7.3 lE+OO 9.15E+Ol A-15
Table A-6 (Continued)
Palisades Cycle 8 Reactor Cavity Gradient Chain Measurements Reference Azimuth: 150 deg.
Bead Chain Tag ID: (NONE)
Chain Composition Fe: 0.667 Ni: 0.0906 Co: 0.00131 Feet [ <----------- dps/mg of chain @ 12/ 12/90 -----------> J from Lab - Mn - Co - Co Midplane Sample# dps/mg dps/mg dps/mg
+8.0 90-191 lA 6.13E-01 9.66E-01 3.28E+Ol
+7.5 90-191 lB 9.30E-Ol 1.75E+OO 3.78E+OI
+7.0 90-191 lC 1.77E+OO 3.22E+OO 4.81E+Ol
+6.5 90-191 lD l.70E+OO 3.27E+OO 4.81E+OI
+6.0 90-191 lE 2.50E+OO 4.5 lE+OO 5.24E+OI
+5.5 90-191 lF 3.80E+OO 6.34E+OO 5.56E+Ol
+5.0 90-191 lG 4.53E+OO 7.93E+OO 6.1 lE+Ol
~~+4.5~~
+4.0
+3.5
+3.0
+2.5 90-191 lH 90-19111
.90-191 lJ 90-191 lK 90-191 lL 4.99E+OO 5.76E+OO 6.89E+OO 6.75E+OO 7.02E+OO l.02E+Ol l.08E+Ol l.13E+Ol l.21E+Ol
~~l. l9E+Ol 6.54E+Ol 6.93E+Ol 7.38E+O 1 7.79E+Ol 8.07E+Ol~~
+2.0 90-191 lM 7.32E+OO l.29E+Ol 8.37E+Ol
+1.5 90-191 lN 7.23E+OO l.21E+Ol 8.66E+O 1
+1.0 90-19110 7.61E+OO l. l8E+Ol 8.88E+Ol
+0.5 90-191 lP 7.35E+OO l.21E+Ol 9.06E+OI 0.0 90-191 lQ 7.67E+OO l.32E+Ol 9. l6E+Ol
-0.5 90-191 lR 7.26E+OO l.27E+Ol 9. l9E+OI
-1.0 90-1911S 7.38E+OO 1.14E+Ol 9.13E+Ol
-1.5 90-19 llT 7.20E+OO l.18E+Ol 8.98E+Ol
-2.0 90-191 lU 7.02E+OO 1.22E+Ol 8.89E+Ol
-2.5 90-1911 v 6.94E+OO 1.15E+Ol 8.59E+Ol
-3.0 90-1911 w 6.22E+OO l.19E+Ol 8.43E+Ol
-3.5 90~19 l lX 6.l5E+OO l.08E+Ol 7.89E+O I
-4.0 90-1911 y 5.67E+OO 9.58E+OO 7.49E+Ol
-4.5 90-191 lZ 4.78E+OO 8.45E+OO 6.80E+Ol A-16
Table A-6 (Continued)
~~Palisades Cycle 8 Reactor Cavity Gradient Chain Measurements Reference Azimuth: 210 deg.~~
Bead Chain Tag ID: 210 Chain Composition Fe: 0.665 Ni: 0.0865 Co: 0.00179 Feet [<----------- dps/mg of chain @ 12/ 12/90 -----------> J from Lab - Mn - Co - Co Mid plane Sample# dps/mg dps/mg dps/mg
+8.0 90-l912A 5.16E-Ol . 9.26E-Ol 4.20E+OI
+7.5 90-1912B 7.64E-Ol l.35E+OO 4.83E+Ol
+7.0 90-1912C l.04E+OO l.93E+OO 5.57E+Ol
+6.5 90-19120 l.47E+OO 3.00E+OO 6.22E+Ol
+6.0 90-1912E 2.48E+OO 4.68E+OO 6.70E+Ol
+5.5 90-1912F *3.39E+OO 5.92E+OO 7.2 lE+O l
+5.0 90-19120 4.31E+OO 7.77E+OO 7.82E+Ol
+4.5 90-1912H 5.22E+OO 9.40E+OO 8.56E+Ol
+4.0 90-19121 5.73E+OO 9.7 IE+OO 9.06E+OI
+3.5 90-19121 6.35E+OO l.04E+Ol 9.68E+Ol
+3.0 90-1912K 6.50E+OO l.13E+Ol 9.97E+Ol
+2.5 90-1912L 7.28E+OO l.07E+Ol l.04E+02
+2.0 90-1912M 6.76E+OO l.19E+Ol l.07E+02
+1.5 90-l912N 6.96E+OO l.17E+Ol l.l2E+02
+l.O 90-19120 6.86E+OO l.12E+Ol I. l4E+02
+0.5 90-1912P 6.98E+OO l.22E+Ol l .16E+02 0.0 90-1912Q 6.62E+OO l. l7E+Ol l.21E+02
-0.5 90-1912R 7.29E+OO l.19E+Ol 1.20E+02
-1.0 90-19125 6.89E+OO l.18E+Ol l.20E+02
-1.5 90-1912T 6.92E+OO l.27E+Ol 1.18E+02
-2.0 90-1912U 7.16E+OO l.19E+Ol l.16E+02
-2.5 90-1912V 6.5 IE+OO l.09E+Ol l. l lE+02
-3.0 90-1912W 6. l9E+OO l.04E+Ol l.05E+02
-3.5 90~1912X 6.26E+OO 9.99E+OO l.OOE+02
-4.0 90-1912Y 5.14E+OO 9.45E+OO 9.28E+Ol
-4.5 90-19122 4.21E+OO 8.06E+OO 8.42E+O l A-17
Table A-6 (Continued)
~~Palisades CyCle 8 Reactor Cavity Gradient Chain Measurements Reference Azimuth: 340 deg.~~
Bead Chain Tag ID: 150 Chain Composition Fe: 0.684 Ni: 0.0941 Co: 0.00186 Feet [<----------- dps/mg of chain @ 12/ 12/90 -----------> j from Lab - Mn - Co - Co Mid plane Sample# dps/mg dps/mg lips/mg
+8.0 90-1920A 7.82E-Ol l.27E+OO 4.25E+Ol
+7.5 90-19208 8.18E-Ol 2.32E+OO 4.65E+Ol
+7.0 90-l 920C l.36E+OO 2.55E+OO 5.38E+O l
+6.5 90-19200 2.05E+OO 3.53E+OO 5.62E+Ol
+6.0 90-1920E 2.68E+OO 5.55E+OO 6.53E+Ol
+5.5 90-1920F 3.98E+OO 7.26E+OO 6.82E+Ol
+5.0 90-19200 4.92E+OO 8.42E+OO 7.57E+Ol
+4.5 90-1920H 5.65E+OO 1.02E+Ol 8.19E+Ol
+4.0 90-19201 6.61E+OO l.07E+Ol 8.78E+Ol
+3.5 90-19201 7.20E+OO . l.15E+Ol 9.0lE+Ol
+3.0 90-1920K 7.88E+OO l.24E+Ol 9.73E+Ol
+2.5 90-1920L 8.08E+OO l.32E+Ol 9.98E+Ol
+2.0 90-1920M 8.21E+OO l.34E+Ol l.07E+02
+l.5 90-1920N 8.18E+OO l.34E+Ol 1.11 E+02
+1.0 90-19200 7.65E+OO l.35E+Ol l.12E+02
+0.5 90-1920P 7.89E+OO l.36E+Ol l.18E+02 0.0 90-1920Q 8.29E+OO 1.29E+Ol l.20E+02
-0.5 90-1920R 8.00E+OO l.39E+Ol 1. l 9E+02
-1.0 90-19205 7.96E+OO l.40E+Ol l.22E+02
-1.5 90-1920T 7.96E+OO l.45E+Ol l.18E+02
-2.0 90-1920U 8.22E+OO l.42E+Ol l.19E+02
-2.5 90-1920V 8.09E+OO l.36E+Ol l.16E+02
-3.0 90-1920W 7.31E+OO l.25E+Ol l.09E+02
-3.5 90-1920X 6.94E+OO l.09E+Ol l.07E+02
-4.0 90-1920Y 6.14E+OO l.05E+Ol 9.83E+Ol
-4.5 90-1920Z 2.02E+OO 3.22E+OO 3.24E+Ol A-18
Table A-6 (Continued)
Palisades Cycle 8 Reactor Cavity Gradient Chain Measurements Reference Azimuth: 260 deg.
Bead Chain Tag ID: (NONE)
Chain Composition Fe: 0.672 Ni: 0.09 Co: 0.00165 Feet [<----------- dps/mg of chain @ 12/ 12/90 -----------> l from Lab - Mn - Co - Co Mid plane Sample# dps/mg dps/mg dps/mg
+8.0 90-1913A 6.58E-Ol ~ l.36E+OO 3.44E+Ol
+7.5 90-19138 8.56E-Ol l.58E+OO 3.94E+Ol
+7.0 90-! 913C l.33E+OO 2.34E+OO 4.29E+Ol
+6.5 90-1913D l.77E+OO 2.65E+OO 4.49E+Ol
+6.0 90-1913E 8.96E-Ol 2.25E+OO 4.09E+Ol
+5.5 90-1913F 5.38E-01 l.35E+OO 3.68E+Ol
+5.0 90-19130 5.42E-Ol 9.06E-Ol 3. lOE+Ol
+4.5 90-l913H 4.69E-Ol 5.9 lE-O l 2.77E+Ol
+4.0 90-19131 2.73E-01 4.49E-Ol 2.63E+O!
+3.5 90-19131 l.74E-Ol 5.05E-Ol 2.15E+Ol
+3.0 90-1913K 1.68E-O 1 4.23E-01 2.06E+Ol
+2.5 90-1913L l.93E-01 2.08E-Ol l.69E+Ol
+2.0 90-1913M l.27E-01 2.88E-Ol l.51E+Ol
+l.5 90-1913N l.32E-O l ND l.25E+Ol
+l.O 90-19130 ND ND l.06E+OI
+0.5 90-1913P ND ND 8.97E+OO 0.0 90-1913Q ND ND 8.03E+OO
-0.5 90-1913R ND ND 7.07E+OO
-1.0 90-1913S ND 8.13E-02 7.00E+OO
-1.5 90-1913T 5.91E-02 ND 6.3 lE+OO
-2.0 90-19130 ND ND 5.87E+OO
-2.5 90-1913V ND ND 5.42E+OO
-3.0 90-1913W ND ND 5.22E+OO
-3.5 90.,1913X ND ND 4.83E+OO
-4.0 90-l913Y ND ND 4.44E+OO
-4.5 90-1913Z ND ND 4.28E+OO
~~ND indicates that activity was not detected.~~
A-19
Table A-7 Palisades Cycle 9 Reactor Cavity Dosimetry Set Results Lab Dosimeter Foil ID Sample# Material Nuclide dps/mg A 92-719 Fe Mn-54 l.91E+OI K 92-720 Fe Mn-54 I .84E+O I c 92-732 Fe Mn-54 3.59E+OO M 92-733 Fe Mn-54 3.22E+OO F 92-745 Fe Mn-54 7.72E+OO p 92-746 Fe Mn-54 7.5 lE+OO c 92-758 Fe Mn-54 l .48E+OI M 92-759 Fe Mn-54 1.44E+Ol D 92-771 Fe Mn-54 l.22E+OI N 92-772 Fe Mn-54 l.21E+Ol E 92-784 Fe Mn-54 3.95E+OO 0 92-785 Fe Mn-54 3.69E+OO G 92-797 Fe Mn-54 8.58E+OO R 92-798 Fe Mn-54 8.22E+OO A 92-721 Ni Co-58 3.16E+02 c 92-734 Ni Co-58 6.02E+Ol F 92-747 Ni Co-58 l.04E+02 0 92-760 Ni Co-58 3.48E+02 p 92-773 Ni Co-58 2.94E+02 R 92-786 Ni Co-58 9.52E+Ol T 92-799 Ni Co-58 2.0IE+02 BA 92-722 Cu Co-60 9.62E-Ol BC 92-735 Cu Co-60 1.46E-O I BF 92-748 Cu Co-60 4.86E-Ol AO 92-761 Cu Co-60 4.65E-OI AP 92-774 Cu Co-60 3.99E-OI AR 92-787 Cu Co-60 l.llE-01 AT 92-800 Cu Co-60 2.76E-Ol
~~dps I (mg of dosimeter material) on March 4, 1992.~~
A-20
Table A-7 (Continued)
Palisades Cycle 9 Reactor Cavity Dosimetry Set Results Lab Dosimeter Foil ID Sample# Material Nuclide dps/mg A 92-725 Co-Al . Co-60 4.27E+02 K 92-726 Co-Al Co-60 2.69E+02 c 92-738 Co-Al Co-60 2.15E+02 M 92-739 Co-Al Co-60 l.49E+02 F 92-751 Co-Al Co-60 3.14E+02 p 92-752 Co-Al Co-60 2.16E+02 0 92-764 Co-Al Co-60 l.77E+02 AO 92-765 Co-Al Co-60 l. l 7E+02 p 92-777 Co-Al Co-60 l.58E+02 AP 92-778 Co-Al Co-60 l.13E+02 R 92-790 Co-Al Co-60 9.50E+Ol AR 92-791 Co-Al Co-60 6.43E+Ol T 92-803 Co-Al Co-60 l.76E+02 AT 92-804 Co-Al Co-60 I. l 1E+02 AK 92-723 Ti Sc-46 6.73E+OO AM 92-736 Ti Sc-46 l.14E+OO AP 92-749 Ti Sc-46 2.07E+OO BE 92-762 Ti Sc-46 7.24E+OO BF 92-775 Ti Sc-46 6.12E+OO BG 92-788 Ti Sc-46 l.82E+OO BI 92-801 Ti Sc-46 4.16E+OO
~~dps / (mg of dosimeter material) on March 4, 1992.~~
~~A-21~~
~~Table A-7 (Continued)~~
Palisades Cycle 9 Reactor Cavity Dosimetry Set Results Lab Dosimeter Foil ID Sample# Material Nuclide dps/mg 8 92-731 Np-237 Zr-95 3.28E+02 10 92-744 Np-237 Zr-95 7.95E+Ol 13 92-757 Np-237 Zr-95 l.24E+02 16 92-768 Np-237 Zr-95 3.65E+02 17 92-781 Np-237 Zr-95 2.82E+02 18 92-794 Np-237 Zr-95 1.17E+02 20 92-807 Np-237 Zr-95 2.13E+02 8 92-731 Np-237 Ru-103 3.08E+02 10 92-744 Np-237 Ru-103 8.40E+O I 13 92-757 Np-237 Ru-103 l.16E+02 16 92-768 Np-237 Ru-103 3.42E+02 17 92-781 Np-237 Ru-103 2.87E+02 18 92-794 Np-237 Ru-103 l.13E+02 20 92-807 Np-237 Ru-103 2.22E+02 8 92-731 Np-237 Cs-137 2.81E+Ol 10 .92-744 Np-237 Cs-137 7.03E+OO 13 92-757 Np-237 Cs-137 1.57E+O 1 16 92-768 Np-237 Cs-137 1.15E+Ol 17 92-781 Np-237 Cs-137 l.09E+Ol 18 92-794 Np-237 Cs-137 3.40E+OO 20 92-807 Np-237 Cs-137 6.45E+OO

~~dps I (mg of dosimeter material) on March 4, 1992.~~
A-22
Table A-7 (Continued)
Palisades Cycle 9 Reactor Cavity Dosimetry Set Results Lab Dosimeter Foil ID Sample# Material Nuclide dps/mg AA 92-727 U (nat) Zr-95 6.22£+0 l BG 92-728 U (dep) Zr-95 2.0lE+Ol 11 92-729 U (dep) Zr-95 2.1 OE+O I Nl 92-730 U (nat) Zr-95 6.18E+Ol AC 92-740 U (nat) Zr-95 3.33E+O 1 BI 92-741 U (dep) Zr-95 5.66E+OO 13 92-742 U (dep) Zr-95 4.77E+OO N3 92-743 U (nat) Zr-95 3.15E+Ol AF 92-753 U (nat) Zr-95 3.67E+Ol AM 92-754 U (dep) Zr-95 7.43E+OO 16 92-755 U (dep) Zr-95 6.63E+OO N6 92-756 U (nat) Zr-95 3.48E+Ol c 92-766 U (nat) Zr-95 6.66E+Ol c 92-767 U (dep) Zr-95 2.32E+Ol D 92-779 U (nat) Zr-95 6.12E+Ol D 92-780 U (dep) Zr-95 2.21E+Ol E 92-792 U (nat) Zr-95 3.50E+Ol E 92-793 U (dep) Zr-95 7.33E+OO G 92-805 U (nat) Zr-95 l.62E+02 u 92-806 U (dep) Zr-95 l .43E+Ol
~ dps I (mg of dosimeter material) on March 4, 1992.
A-23
~~Table A-7 (Continued)~~
~~Foil ID Palisades- Cycle 9 Reactor Cavity Dosimetry Set Results Lab Sample#~~
Dosimeter Material Nuclide dps/mg AA 92-727 U (nat) Ru-103 4.37E+O I BG 92-728 U (dep) Ru-103 2.08E+O I 11 92-729 U (dep) Ru-103 2.20E+O I NI 92-730 U (nat) Ru-103 4.26E+O I AC 92-740 U (nat) Ru-103 l.73E+O I BI 92-741 U (dep) Ru-103 5.12E+OO 13 92-742 U (dep) Ru-103 4.70E+OO N3 92-743 U (nat) Ru-103 l.63E+Ol AF 92-753 U (nat) Ru-103 2.12E+Ol AM 92-754 U (dep) Ru-103 6.91 E+OO 16 92-755 U (dep) Rti-103 7.19E+OO N6 92-756 U (nat) Ru-103 l.96E+Ol c 92-766 U (nat) Ru-103 4.70E+O I c 92-767 U (dep) Ru-103 2.31E+Ol D 92-779 U (nat) Ru-103 4.17E+Ol D 92-780 U (dep) Ru-103 l.94E+Ol E 92-792 U (nat) Ru-103 l.96E+Ol E 92-793 U (dep) Ru-103 6.87E+OO G 92-805 U (nat) Ru-103 l.02E+02 u 92-806 U (dep) Ru-103 l.29E+Ol

~~dps I (mg of dosimeter material) on March 4, 1992.~~
A-24
Table A-7 (Continued)
~~Foil ID Palisades Cycle 9. Reactor Cavity Dosimetry Set Results Lab Sample#~~
Dosimeter Material Nuclide dps/mg AA 92-727 U (nat) Cs-137 5.42E+OO BG 92-728 U (dep) Cs-137 l.6XE+OO 11 92-729 U (dep) Cs-137 l .X4E+OO Nl 92-730 U (nat) Cs-137 5.36E+OO AC 92-740 U (nat) Cs-137 2.32E+OO BI 92-741 U (dep) Cs-137 4.17E-O 1 13 92-742 U (dep) Cs-137 3.46E-O 1 N3 92-743 U (nat) Cs-137 2.19E+OO AF 92-753 U (nat) Cs-137 3.6 lE+OO AM 92-754 U (dep) Cs-137 8.97E-O 1 16 92-755 U (dep) Cs-137 9.21E-Ol N6 92-756 U (nat) Cs-137 3.57E+OO c 92-766 U (nat) Cs-137 2.21E+OO c 92-767 U (dep) Cs-137 7.35E-01 D 92-779 U (nat) Cs-137 1.92E+OO D 92-780 U (dep) Cs-137 7.16E-01 E 92-792 U (nat) Cs-137 9.48E-O 1 E 92-793 U (dep) Cs-137 2. lOE-01 G 92-805 U (nat) Cs-137 5.16E+OO u 92-806 U (dep) Cs-137 4.67E-01
~~dps I (mg of dosimeter material) on March 4, 1992.~~
A-25
(This page intentionally left blank.)
A-26
Table A-8
~~Palisades Cycle 9 Reactor Cavity Gradient Chain Measurements Reference Azimuth: 270 deg.~~
Bead Chain Tag ID: 270 Chain Composition Fe: 0.7088 Ni: 0.09768 Co: 0.00175 Feet [<----------- dps/rng of chain @ 3/4/92 ----------->I from Lab - Mn - Co - Co Midplane Sample# dps/rng dps/rng dps/mg
+0.5 92-712A 1.18E+Ol 2.91E+Ol l.54E+02
-0.5 92-712C l.15E+Ol 2.84E+Ol l.54E+02
-1.0 92-7120 1.13E+Ol 2.76E+Ol l.5 !E+02
-1.5 92-712E l.lOE+Ol 2.53E+Ol l.47E+02
-2.0 92-712F 9.39E+OO 2.50E+Ol l.45E+02
-2.5 92-7120 8.79E+OO 2.20E+Ol l.33E+02
-3.0 92-712H 7. IOE+OO I.82E+OI l.35E+02
-3.5 92-7121 6.70E+OO l.62E+Ol l.26E+02
-4.0 92-712J 6.42E+OO l.48E+Ol l.15E+02
-4.5 92-712K 3.93E+OO l.02E+Ol 9.39E+Ol
-5.0 92-712L 2.76E+OO 7.33E+OO 8.33E+Ol
-5.5 A-27
Table A-8 (Continued)
~~Palisades Cy-cle 9 Reactor Cavity Gradient Chain Measurements Reference Azimuth: 280 deg.~~
Bead Chain Tag ID: S-2 280 Chain Composition Fe: 0.7213 Ni: 0.09887 Co: 0.00143 Feet [<----------- dps/mg of chain @ 3/4/92 -----------> l from Lab - Mn - Co - Co Midplane Sarnple# dps/mg dps/mg dps/mg
+0.5 92-713A 9.33E+OO 3.25E+Ol 4.83E+O l
-0.5 92-713C 9.43E+OO 3.20E+OI 4.84E+OI
-1.0 92-7130 9.41E+OO 3.1 lE+O l 4.79E+OI
-1.5 92-713E 8.97E+OO 3.03E+Ol 4.71E+OI
-2.0 92-713F 8.29E+OO 2.87E+Ol 4.60E+O l
-2.5 92-713G 7.84E+OO 2.69E+OI 4.49E+OI
-3.0 92-713H 7.00E+OO 2.49E+Ol 4.32E+O I
-3.5 92-7131 6.53E+OO 2.29E+Ol 4. lOE+Ol
-4.0 92-7131 5.38E+OO l.90E+Ol 3.88E+Ol
-4.5 92-713K 3.93E+OO. l .48E+O l 3.37E+O I
-5.0 92-713L 2.81E+OO l.03E+Ol 2.84E+Ol
-5.5 92-713M 2.15E+OO 7.58E+OO 2.69E+O I A-28
Table A-8 (Continued)
~~Palisades Cycle 9 Reactor Cavity Gradient Chain Measurements Reference Azimuth: 290 deg.~~
Bead Chain Tag ID: S-2 290 Chain Composition Fe: 0.6913 Ni: 0.10184 Co: 0.00139 Feet [<----------- dps/mg of chain @ 3/4/92 -----------> J from Lab - Mn - Co - Cu-oo -
Midplane
~~Sample# dps/mg dps/mg dps/mg~~
+0.5 92-714A 7.93E+OO 2.67E+Ol 4.38E+O I
-0.5 92-714C 8.12E+OO 2.71E+Ol 4.43E+Ol
-1.0 92-7140 7.64E+OO 2.70E+Ol 4.44E+Ol
-1.5 92-714E 7.98E+OO 2.64E+Ol 4.37E+Ol
-2.0 92-714F 7.39E+OO 2.55E+Ol 4.3 lE+O l
-2.5 92-7140 6.99E+OO 2.46E+Ol 4.18E+Ol
-3.0 92-714H 6.42E+OO 2.32E+Ol 4.1 lE+Ol
-3.5 92-7141 6.0lE+OO 2.19E+Ol 3.94E+Ol
-4.0 92-714J 5.61E+OO l.93E+Ol 3.75E+O I
-4.5 92-714K 4.58E+OO l.65E+Ol 3.52E+O l
-5.0 92-714L 3.20E+OO l.12E+Ol 2.85E+Ol
-5.5 A-29
Table A-8 (Continued)
~~Palisades Cycle 9 Reactor Cavity Gradient Chain Measurements Reference Azimuth: 300 deg.~~
Bead Chain Tag ID: 300 Chain Composition Fe: 0.7197 Ni: 0.10234 Co: 0.00178 Feet [<----------- dps/mg of chain @ 3/4/92 -----------> l from Lab - Mn - Co - Co Midplane S::unple# dps/mg dps/mg dps/mg
+0.5 92-715A 5.38E+OO 1.33E+Ol l. IXE+02
-0.5 92-715C 4.68E+OO 7.21E+OO l.07E+02
-1.0 92-7150 3.73E+OO 5. lOE+OO l.05E+02
-1.5 92-715E 3.49E+OO 3. lOE+OO l.03E+02
-2.0 92-715F 2.52E+OO 2.50E+OO l.OOE+02
-2.5 92-715G 2.46E+OO l.75E+OO 9.62E+Ol
-3.0 92-715H 2.l3E+OO l.l3E+OO 9.24E+Ol
-3.5 92-7151 2.1 lE+OO l.20E+OO 8.82E+Ol
-4.0 92-7151 2.13E+OO 7.8lE-O1 8.40E+Ol
-4.5 92-715K l.65E+OO 8.00E-01 7.84E+Ol
-5.0 92-715L l.32E+OO 6.0SE-01 6.89E+Ol
-5.5 92-715M 8.33E-Ol 7.42E-Ol 5.97E+Ol A-30
Table A-8 (Continued)
~~.Palisades Cycle 9 Reactor Cavity Gradient Chain Measurements Reference Azimuth: 315 deg.~~
Bead Chain Tag ID: S-2 315 Chain Composition Fe: 0.7073 Ni: 0.10112 Co: CUJO 14 Feet [<----------- dps/mg of chain @ 3/4/92 ----------->I from Lab - Mn - Co - Co Midplane Sample# dps/mg dps/mg dps/mg
+0.5 92-716A 5.52E+OO l.84E+Ol 4.85E+Ol
-0.5 92-716C 5.58E+OO l.83E+Ol 4.89E+O I
- l.O 92-7160 5.46E+OO l.80E+Ol 4.83E+Ol
-l.5 92-716E 4.82E+OO l.72E+Ol 4.77E+Ol
-2.0 92-716F 4.68E+OO l.66E+Ol 4.65E+Ol
-2.5 92-716G 4.42E+OO l.53E+Ol 4.5 !E+Ol
-3.0 92-716H 4.37E+OO l.45E+Ol 4.33E+Ol
-3.5 92-7161 3.91E+OO l.34E+OI 4.12E+OI
-4.0 92-7161 3.30E+OO l.16E+Ol 3.85E+Dl
-4.5 92-716K 2.82E+OO l.OlE+Ol 3.54E+Ol
-5.0 92-716L 2.16E+OO 7.35E+OO 2.72E+Ol
-5.5 92-716M l.66E+OO 5.67E+OO 2.38E+O 1 A-31
Table A-8 (Continued)
Palisades Cycle 9 Reactor Cavity Gradient Chain Measurements Reference Azimuth: 330 deg.
Bead Chain Tag ID: S-2 330 Chain Composition Fe: 0.7293 Ni: 0.10402 Co: 0.00142 Feet [ <----------- dps/mg of chain @ 3/4/92 -----------> l from Lab -Mn -Co -Co Mid plane Sample# dps/mg dps/mg dps/mg
+0.5 92-717 A 7.92E+OO 2.68E+Ol 5.43E+U l 0.0 92-717B 8.07E+OO 2.68E+Ol 5.36E+Ol
-0.5 92-717C 7.76E+OO 2.65E+Ol 5.39E+O l
-1.0 92-717D 7.93E+OO 2.63E+Ol 5.34E+Ol
-1.5 92-717E 7.69E+OO 2.6 lE+Ol 5.26E+Ol
-2.0 92-717F 7.5 lE+OO 2.54E+Ol 5.13E+O l
-2.5 92-7170 6.93E+OO 2.40E+Ol 4.97E+Ol
-3.0 92-717H 6.49E+OO 2.24E+Ol 4.76E+Ol
-3.5 92-7171 5.82E+OO 2.05E+Ol 4.49E+Ol
-4.0 92-7171 5.0lE+OO l.78E+Ol 4.18E+Ol
-4.5 92-717K 4.0lE+OO l.47E+Ol 3.84E+Ol
-5.0 92-7 l 7L 2.68E+OO 9.75E+OO 2.96E+Ol
-5.5 92-717M 2.1 lE+OO 7.1 lE+OO 2.64E+Oi A-32
. Table A-8 (Continued)
Palisades Cycle 9 Reactor Cavity Gradient Chain Measurements Reference Azimuth: 30 deg.
Bead Chain Tag ID: S-2 30 Chain Composition Fe: 0.7167 Ni: 0.09729 Co: o.uo 135 Feet [<----------- dps/mg of chain @ 3/4/92 -----------> l from Lab - Mn - Co - Co Midplane Sample# dps/mg dps/mg dps/mg
+8.0 92-707A 4.54E-OI l.72E+OO l .96E+O l
+7.5 92-707B 6.33E-OI 2.51E+OO 2.24E+OI
+7.0 92-707C l.02E+OO 3.82E+OO 2.47E+O I
+6.5 92-707D I.57E+OO 5.63E+OO 2.68E+O l
+6.0 92-707E 2.29E+OO 7.69E+OO 2.88E+OI
+5.5 92-707F 2.99E+OO l.09E+Ol 3. 15E+Ol
+5.0 92-7070 3.84E+OO l.3IE+Ol 3.4IE+O I
~~+4.5~~
+4.0
+3.5
+3.0
+2.5 92-707H 92-7071 92-707J 92-707K 92-707L 4.38E+OO 5.09E+OO 5.48E+OO 5.77E+OO 6.00E+OO l.56E+Ol l.72E+Ol l.88E+Ol l.93E+Ol 2.03E+Ol 3.64E+Ul 3.84E+O l 4.02E+Ol 4.20E+OI 4.34E+OI
+2.0 92-707M 5.89E+OO 2.08E+Ol 4.48E+O 1
+1.5 92-707N 6.lOE+OO 2.08E+Ol 4.64E+Ul
+l.O 92-7070 6.14E+OO 2.1 lE+Ol 4.74E+OI
+0.5 92-707P 6.28E+OO 2.13E+Ol 4.88E+Ol 0.0 92-707Q 6.33E+OO 2.08E+Ol 4.90E+OI
-0.5 92-707R 6.37E+OO 2.12E+Ol 4.97E+Ol
-1.0 92-707S 6.09E+OO 2.14E+Ol 4.95E+OI
-1.5 92-707T 6.30E+OO 2.14E+Ol 4.96E+Ol
-2.0 92-707U 6.16E+OO 2.14E+Ol 4.9IE+Ol
-2.5 92-707V 6.06E+OO 2. lOE+Ol 4.79E+Ul
-3.0 92-707W 6.00E+OO l.98E+Ol 4.63E+OI
-3.5 92-707X 5.21E+OO 1.8 lE+Ol 4.40E+Ol
-4.0 92-707Y 4.62E+OO l.66E+Ol 4. I 3E+OI
-4.5 92-707Z 4.08E+OO l.40E+Ol 3.79E+OI A-33 J
Table A-8 (Continued)
~~Palisades Cycle 9 Reactor Cavity Gradient Chain Measurements Reference Azimuth: 90 deg.~~
Bead Chain Tag ID: S-2 90 Chain Composition Fe: 0.7136 Ni: 0.09781 Co: 0.00139 Feet [<----------- dps/mg of chain @ 3/4/92 -----------> l from Lab - Mn - Co - Co Midplane Sample# dps/mg dps/mg dps/mg
+8.0 92-708A 5.53E-Ol 2.17E+OO 2.14E+O l
+7.5 92-7088 8.56E-01 3.56E+OO 2.49E+Ol
+7.0 92-708C 1.43E+OO 5.09E+OO 2.77E+Ol
+6.5 92-7080 2.16E+OO 7.36E+OO 3.05E+Ol
+6.0 92-708E 3.1 IE+OO l.04E+Ol 3.3 lE+Ol
+5.5 92-708F 4.06E+OO l.39E+Ol 3.64E+Ol
+5.0 92-708G 4.93E+OO l.73E+Ol 3.93E+Ol
+4.5 92-708H 5.91E+OO 2.05E+Ol 4.25E+OI
+4.0 92-7081 6.33E+OO 2.27E+Ol 4.56E+Ol
+3.5 92-708J 7.1 lE+OO 2:45E+Ol 4.80E+Ol
+3.0 92-708K 7.43E+OO 2.57E+Ol 5. IOE+Ol
+2.5 92-708L 7.69E+OO 2.59E+Ol 5.30E+Ol
+2.0 92-708M 7.70E+OO 2.59E+Ol 5.3 lE+Ol
+l.5 92-708N 7.79E+OO 2.65E+Ol 5.76E+Ol
+l.O 92-7080 8.04E+OO 2.69E+Ol 5.95E+Ol
+0.5 92-708P 7.96E+OO 2.68E+Ol 6.04E+Ol 0.0 92-708Q 8.05E+OO 2.64E+Ol 6. l 3E+O I
-0.5 92-708R 8.0lE+OO 2.63E+Ol 6.13E+Ol
-1.0 92-708S 8.02E+OO 2.61E+Ol 6.16E+Ol
-1.5 92-708T 7.13E+OO 2.48E+Ol 6.08E+Ol
-2.0 92-7080 6.96E+OO 2.40E+Ol 5.95E+Ol
-2.5 92-708V 6.40E+OO 2.30E+Ol 5.69E+Ol
-3.0 92-708W 6.42E+OO 2.16E+Ol 5.46E+Ol
-3.5 92-708X 6.0lE+OO 2.02E+Ol 5.14E+Ol
-4.0 92-708Y 5.33E+OO 1.83E+Ol 4.84E+Ol
-4.5 92-708Z 4.57E+OO l.56E+Ol 4.3 lE+Ol A-34
Table A-8 (Continued)
Palisades Cycle 9 Reactor Cavity Gradient Chain Measurements Reference Azimuth: 150 deg.
Bead Chain Tag ID: S-2 150 Chain Composition Fe: 0.7207 Ni: 0.09873 Co: 0.00143 Feet [<----------- dps/mg of chain @ 3/4/92 -----------> l from Lab - Mn - Co - Co Midplane Sample# dps/mg dps/mg dps/mg
+8.0 92-709A 4.67E-Ol 1.75E+OO 2.00E+Ol
+7.5 92-7098 7. l6E-Ol 2.48E+OO 2.32E+Ol
+7.0 92-709C l. l6E+OO 4. l 7E+OO 2.69E+Ol
+6.5 92-7090 l.75E+OO 5.98E+OO 2.95E+Ol
+6.0 92-709E 2.29E+OO 8.35E+OO 3.18E+O l
+5.5 92-709F 3.1 lE+OO l.15E+Ol 3.46E+Ol
+5.0 92-7090 3.89E+OO l.42E+Ol 3.70E+Ol
+4.5 92-709H 4.85E+OO l.69E+Ol 4.03E+Ol
+4.0 92-7091 5.2lE+OO 1.8 lE+Ol 4.30E+Ol
+3.5 9-2-709J 5.66E+OO 2.08E+Ol 4.56E+O l
+3.0 92-709K 5.95E+OO 2.l9E+Ol 4.79E+Ol
+2.5 92-709L 6.50E+OO 2.27E+Ol 4.95E+Ol
+2.0 92-709M 6.57E+OO 2.28E+Ol 5. l4E+Ol
+1.5 92-709N 6.94E+OO 2.30E+Ol 5.3 lE+Ol
+1.0 92-7090 6.48E+OO 2.30E+Ol 5.46E+Ol
+0.5 92-709P 6.66E+OO 2.37E+Ol 5.54E+OI 0.0 92-709Q 6.76E+OO 2.37E+Ol 5.63E+Ol
-0.5 92-709R 6.99E+OO 2.38E+Ol 5.68E+Ol
-1.0 92-709S 7.0lE+OO 2.34E+Ol 5.60E+Ol
-1.5 92-709T 6.52E+OO 2.28E+Ol 5.50E+Ol
-2.0 92-709U 6.63E+OO 2.25E+Ol 5.58E+Ol
-2.5 92-709V 6.31E+OO 2.22E+Ol 5.36E+OI
-3.0 92-709W 6.06E+OO 2.13E+Ol 5.24E+Ol
-3.5 92-709X 5.83E+OO 2.03E+Ol 4.96E+Ol
-4.0 92-709Y 5.02E+OO l.82E+Ol 4.67E+Ol
-4.5 92-7092 4.57E+OO l.53E+Ol 4.30E+Ol A-35
Table A-8 (Continued)
Palisades Cycle 9 Reactor Cavity Gradient Chain Measurements Reference Azimuth: 260 deg.
Bead Chain Tag ID: S-2 260 Chain Composition Fe: 0.7116 Ni: 0.0958 l Co: 0.00138 Feet [<----------- dps/mg of chain @ 3/4/92 ----------->I from Lab - Mn - Co - Cn Midplane Sample# dps/mg dps/mg Lips/mg
+8.0 92-7llA 5.0lE-01 l.89E+OO 2.16E+Ol
+7.5 92-71 lB 7.43E-Ol 2.89E+OO 2.42E+Ol
+7.0 92-71 lC l.22E+OO 4.40E+OO 2.68E+Ol
+6.5 92-71 lD l.92E+OO 6.63E+OO 2.95E+Ol
+6.0 92-711E 2.65E+OO 9.44E+OO 3. l 9E+Ol
+5.5 92-711F 3.70E+OO l.26E+Ol 3.44E+Ol
+5.0 92-71 lG 4.62E+OO l.66E+Ol 3.68E+Ol
+4.5 92-71 lH 5.47E+OO l.94E+Ol 3.93E+Ol
+4.0 92-7111 6.20E+OO 2.17E+Ol 4.12E+Ol
+3.5 92-7 l lJ 6.73E+OO 2.37E+Ol 4.31E+OI
+3.0 92-71 lK 7.34E+OO 2.49E+Ol 4.52E+Ol
+2.5 92-7llL 7.63E+OO 2.57E+Ol 4.66E+OI
+2.0 92-711M 7.46E+OO 2.58E+Ol 4.82E+OI
+1.5 92-711N 7.53E+OO 2.62E+Ol 4.93E+Ol
+l.O 92-7110 7.90E+OO 2.65E+Ol 5.07E+Ol
+0.5 92-71 lP 8.08E+OO 2.66E+Ol 5.16E+OI 0.0 92-71 lQ 8.04E+OO 2.68E+Ol 5.18E+Ol.
-0.5 92-711R 8.04E+OO 2.70E+Ol 5.25E+Ol
-1.0 92-71 lS 8.07E+OO 2.73E+Ol 5.21E+Ol
-1.5 92-71 lT 8.20E+OO 2.73E+Ol 5.15E+Ol
-2.0 92-711 u 7.96E+OO 2.63E+Ol 5.05E+Ol
-2.5 92-71 lV 7.47E+OO 2.52E+Ol 4.94E+Ol
-3.0 92-71 lW 7.05E+OO 2.42E+Ol 4.73E+Ol
-3.5 92~7 l lX 6.68E+OO 2.24E+Ol 4.53E+Ol
-4.0 92-71 lY 5.73E+OO 2.03E+Ol 4.27E+Ol
-4.5 92-711Z 4.84E+OO l.72E+Ol 3.89E+O I A-36
Table A-8 (Continued)
Palisades Cycle 9 Reactor Cavity Gradient Chain Measurements A-37
Table A-9 Palisades Cycle 9 In-Vessel Dosimetry Capsule Results Lab Sample# Capsule Dosimeter Material Nuclide dps/mg 92-1133 lAlF Fe Mn-54 1.12E+03 92-1142 1A4F Fe Mn-54 1.28E+03 92-115 l lA7F Fe Mn-54 l.24E+03 92-1137 lAlF Cu Co-60 3.59E+Ol 92-1146 1A4F Cu Co-60 3.88E+Ol 92-1155 1A7F Cu Co-60 3.83E+Ol 92-1136 lAlF Ni Co-58 2.71E+04 92-1145 1A4F Ni Co-58 2.74E+04 92-1154 1A7F Ni Co-58 2.84E+04
. 92-1132 lAlF Ti Sc-46 6.28E+02 92-1141 1A4F Ti Sc-46 6.97E+02 92-1150 1A7F Ti Sc-46 6.78E+02 92-1131 lAlF U02 Zr-95 l.20E+03 92-1140 1A4F U02 Zr-95 1.35E+03 92-1149 1A7F U02 Zr-95 l.36E+03 92-1131 lAlF U02 Ru-103 l.31E+03 92-1140 1A4F U02 . Ru-103 l.38E+03 92-1149 1A7F U02 Ru-103 1.47E+03 92-1131 lAlF U02 Cs-137 3.39E+Ol 92-1140 1A4F
U0 2 Cs-137 4.79E+Ol 92-1149 1A7F U02 Cs-137 4.16E+Ol 92-1135 lAlF U02 Zr-95 l.19E+03 92-1144 1A4F U02 Zr-95 l.25E+03 92-1153 1A7F U02 Zr-95 l.26E+03 92-1135 lAlF U02 Ru-103 l.38E+03 92-1144 1A4F U02 Ru-103 1.28E+03 92-1153 1A7F U02 Ru-103 1.40E+03 92-1135 lAlF U02 Cs-137 4.34E+Ol 92-1144 1A4F U02 Cs-137 4.3 lE+O l 92-1153 1A7F U02 Cs-137 4.48E+Ol
~~dps I (mg of dosimeter material) on March 4, 1992.~~
A-38
Table A-9 (continued)
Palisades Cycle 9 In-Vessel Dosimetry Capsule Results Lab Sample# Capsule Dosimeter Material Nuclide dps/mg 92-II38 IA IF Np0 2 Zr-95 5.59E+03 92-1147 1A4F Np0 2 Zr-95 5.80E+03 92-1156 1A7F Np0 2 Zr-95 5.83E+03 92-1I38 lAlF Np0 2 Ru-103 4.92E+03 92-1I47 IA4F Np0 2 Ru-103 5.27E+03 92-1156 1A7F Np0 2 Ru-103 4.98E+03 92-1138 lAlF Np0 2 Cs-137 1.77E+02 92-1147 1A4F Np02 Cs-I37 l.59E+02 92-1156 IA7F Np0 2 Cs-I37 l.90E+02 92-II30 lAIF Al Co Co-60 2.48E+03 92-II39 IA4F Al Co Co-60 2.52E+03 92-1148 1A7F Al Co Co-60 2.48E+03 92-1134 lAlF Al Co Co-60 1.82E+04 92-1143 1A4F Al Co Co-60 I.77E+04 92-1I52 1A7F Al Co Co-60 l.75E+04
~~dps I (mg of dosimeter material) on March 4, 1992.~~
A-39
Figure A-1 Photograph of Cycle 9 In- Vessel Capsule 1A1 F Dosimeters lUil~ I *t I ~ . I~
**1 ..... ,._., * ::L **1. t _,_;, 1
. ' 't l ..
,**--* j ~*r~
'~**.*c,,.,~
A-40 J
Figure A-2
~~Photograph of Cycle 9 In-Vessel Capsule 1A4F Dosimeters A-41~~
Figure A-3 Photograph of Cycle 9 In-Vessel Capsule 1A7F Dosimeters
.... ---*. .. ~,*I" it.
~+*-:-4 f f ., ' . 1*.'"
I I ' ( ' (. t. 1 a: rq.4 g . .
G~@R -. *:.
*&rJA>>
~~A-42~~
Appendix 8 Calculated and Adjusted Flux Spectra This appendix contains tables of absolute calculated and adjusted neutron fluxes at each of the dosimetry positions. (Note that all angles have been shifted into the symmetric position in the first octant.) The calculated fluxes are taken from the DOT R,0 transport calculations as converted by SANDI! into the FERRET 53 group energy structure. This conversion does create some error in group transformation so that integral values calculated from these spectra are not exactly the same as those calculated directly from the DOT output The FERRET code adjusts these group flux values as described in Section 3 to obtain the adjusted flux values for each group. These are tabulated together with the ratio of the calculated to adjusted flux and the FERRET derived uncertainty in each group flux value. These uncertainties are very dependent on the assumptions made about the spectral uncertainty, but the adjustment introduces strong correJations in the group flux errors (these correlations are mainly derived from the reaction rates that are. included in the adjustment). These correlations produce uncertainties in the integral*
values such as fast neutron flux (E > 1.0 Me V) that are generally much lower than the group flux uncertainties themselves. The integral values are tabulated in Sections 5 and 6.
Table B-1 gives the spectrum for the Cycle 9 in-vessel dosimetry capsule for the run described in Table 5-5. Similarly, Table B-2 gives the spectrum for the W-290 surveillance capsule irradiated in the same position in Cycles 1-5. This table corresponds to the run results in Table 5-6. Tables B-3 through B-12 present the spectra for the reactor cavity dosimetry locations and correspond to the results of the runs in Tables 6-11 to 6-20. All of the reactor cavity core midplane locations have absolute calculated fluxes tabulated, but absolute values for the reactor cavity core bottom locations are not available. At these locations, for the dosimetry removed 54 54 after Cycle 9, the core midplane fluxes are renormalized by the ratio of the Fe (n,p) Mn reaction measured at the core bottom dosimetry location to that measured at the core midplane.
B-1
Table B-1 FERRET Spectrum Result - Palisades In- Vessel Capsule at 20° Midplane, Cycle 9 Calculated and Adjusted Group Flux Results Group Energy (Me V) Calculated Flux Adjusted Flux Ratio Uncertainty (n/crn 2-s) (n/crn 2-s) CalcLAdj Flux Percent lcr I.733E+Ol 6.94E+06 5.52E+06 1.26 23 2 1.492E+Ol l.61E+07 1.27E+07 1.27 20 3 I.350E+Ol 7.39E+07 5.83E+07 1.27 17 4 1.162E+Ol l.67E+08 l.32E+08 1.27 15 5 l.OOOE+Ol 4.00E+08 3.19E+08 - 1.25 12 6 8.607E+OO l.01E+09 8.25E+08 1.23 10 7 7.408E+OO l.74E+09 I.45E+09 1.20 10 8 6.065E+OO 2.44E+09 2.09E+09 1.17 10 9 4.966E+OO 4.19E+09 3.69E+09 1.14 9 10 3.679E+OO 3.92E+09 3.56E+09 1.10 11 11 2.865E+OO 6.27E+09 5.89E+09 1.06 11 12 2.231E+OO 5.74E+09 5.53E+09 1.04 13 13 l.738E+OO 5.70E+09 5.54E+09 1.03 14 14 l.353E+OO 4.31E+09 4.18E+09 1.03 16 15 l.108E+OO 5.90E+09 5.72E+09 1.03 18 16 8.208E-Ol 5.32E+09 5.15E+09 1.03 21 17 6.393E-Ol 4.71E+09 4.53E+09 1.04 23 18 4.979E-Ol 3.38E+09 3.23E+09 1.05 25 19 3.877E-Ol 3.85E+09 3.63E+09 1.06 27 20 3.020E-Ol 5.56E+09 5.18E+09 1.07 29 21 1.832E-Ol 4.71E+09 4.35E+09 1.08 30 22 l. l l lE-01 3.82E+09 3.50E+09 1.09 31 23 6.738E-02 3.17E+09 2.88E+09 1.10 32 24 4.087E-02 2.35E+09 2.12E+09 1.11 33 25 2.554E-02 l.63E+09 I.47E+09 1.11 33 26 l.989E-02 l.32E+09 l.18E+09 1.12 34 27 1.503E-02 2.37E+09 2.l 1E+09 1.12 34 28 9.119E-03 2.47E+09 2.18E+09 1.13 60 29 5.53 lE-03 2.70E+09 2.37E+09 1.14 60 B-2
~~Table B-1 (Continued)~~
FERRET Spectrum Result - Palisades In-Vessel Capsule at 20° Midplane, Cycle 9 Calculated and Adjusted Group Flux Results Group Energy (Me V) Calculated Flux Adjusted Flux Ratio Uncertainty
(n/cm2-s) (n/cm 2-s2 Calc[Adj Flux Percent lcr 30 3.355E-03 8.74E+08 7.63E+08 1.14 60 31 2.839E-03 8.46E+08 7.32E+08 1.16 59 32 2.404E-03 8.27E+08 7.06E+08 1.17 59 33 2.035E-03 2.41E+09 2.03E+09 1.19 58 34 l.234E-03 2.35E+09 l.93E+09 1.22 56 35 7.485E-04 2.29E+09 l.83E+09 1.25 54 36 4.540E-04 2.26E+09 l.76E+09 1.28 51 37 2.754E-04 2.35E+09 l.79E+09 1.31 48 38 l.670E-04 2.39E+09 l.64E+09 1.45 19 39 l.013E-04 2.39E+09 l.82E+09 1.32 46 40 6.144E-05 2.39E+09 l.84E+09 1.30 49 41 3.727E-05 2.38E+09 l.87E+09 1.27 51 42 2.260E-05 2.35E+09 l.90E+09 1.24 53 43 l.371E-05 2.33E+09 l.93E+09 1.21 55 44 8.315E-06 2.31E+09 l.94E+09 1.19 56 45 5.043E-06 2.27E+09 l.95E+09 1.17 57 46 3.059E-06 2.23E+09 l.94E+09 1.15 57 47 l.855E-06 2.16E+09 l.90E+09 1.14 58 48 l.125E-06 2.03E+09 l.81E+09 1.12 58 49 6.826E-07 1.92E+09 l.85E+09 1.04 102 50 4.140E-07 l.99E+09 2.14E+09 0.93 100 51 2.5 l lE-07 5.39E+09 6.61E+09 0.82 93 52 l.523E-07 9.l 1E+09 l.27E+l0 0.72 81 53 9.237E-08 l.98E+l0 3.55E+l0 0.56 25 B-3
Table B-2 FERRET Spectrum Result - Palisades W-290 Capsule at 20° Midplane, Cycles 1-5 Calculated and Adjusted Group Flux Results Group Energy (MeV) Calculated Flux Adjusted Flux Ratio Uncertainty (n/cm 2-s) {n/cm 2-s) CalcLAdj Flux Percent lcr l l.733E+Ol l. l lE+07 9.56E+06 1.16 23 2 *l.492E+Ol 2.67E+07 2.28E+07 1.17 20 3 l.350E+Ol l.19E+08 l.OlE+08 1.18 18 4 1.162E+Ol 2.97E+08 2.5 lE+08 1.18 15 5 l.OOOE+Ol 7.10E+08 5.98E+08 1.19 12 6 8.607E+OO l.27E+09 l.08E+09 l.18 11 7 7.408E+OO 3.22E+09 2.74E+09 1.18 10 8 6.065E+OO 4.61E+09 3.96E+09 1.16 10 9 4.966E+OO 8.12E+09 . 7.08E+09 1.15 9 10 3.679E+OO 7.70E+09 6.85E+09 1.12 11 11 2.865E+OO l.23E+ 10 l.13E+l0 1.10 12 12 2.231E+OO l.13E+l0 l.06E+l0 l.07 14 13 l.738E+OO l.13E+ 10 l.07E+l0 l.06 17 14 l.353E+OO 8.52E+09 8.13E+09 l.05 20 15 l.108E+OO l.17E+l0 1.13E+10 l.04 22 16 8.208E-Ol l.05E+10 l.02E+l0 1.03 25 17 6.393E-Ol 9.34E+09 9.10E+09 1.03 27 18 4.979E-01 fr.72E+09 6.55E+09 1.03 29 19 3.877E-01 7.64E+09 7.44E+09 l.03 31 20 3.020E-01 1.1 lE+lO 1.07E+l0 1.03 32 21 l.832E-01 9.39E+09 9.07E+09 1.04 33 22 1.11 lE-Ol 7.60E+09 7.30E+09 1.04 34 23 6.738E-02 6.31E+09 6.03E+09 1.05 35 24 4.087E-02 4.67E+09 4.44E+09 1.05 35 25 2.554E-02 3.25E+09 3.08E+09 1.05 36 26 l.989E-02 2.63E+09 2.48E+09 1.06 36 27 l.503E-02 4.70E+09 4.44E+09 1.06 36 28 9. l 19E-03 4.90E+09 4.61E+09 1.06 62 29 5.531E-03 5.36E+09 5.04E+09 1.06 62 B-4
~~Table B-2 (Continued)~~
FERRET Spectrum Result - Palisades W-290 Capsule at 20° Midplane, Cycles l-5 Calculated and Adjusted Group Flux Results Group Energy (Me V) Calculated Flux Adjusted Flux Ratio Uncertainty (n/cm 2-s) (n/cm 2-s} CalcLAdj Flux Percent la 30 3.355E-03 l.74E+09 l.63E+09 1.06 62 31 2.839E-03 l.68E+09 l.58E+09 l.06 62 32 2.404E-03 l.64E+09 l.54E+09 l.06 62 33 2.035E-03 4.80E+09 4.50E+09 l.07 62 34 l.234E-03 4.67E+09 4.38E+09 1.07 62 35 7.485E-04 4.56E+09 4.28E+09 l.07 62 36 4.540E-04 4.48E+09 4.20E+09 1.07 62 37 2.754E-04 4.66E+09 4.37E+09 1.07 62 38 l.670E-04 4.74E+09 4.45E+09 l.07 62 39 l.013E-04 4.75E+09 4.46E+09 1.07 62 40 6.144E-05 4.75E+09 4.45E+09 l.07 62 41 3.727E-05 4.72E+09 4.43E+09 l.07 62 42 2.260E-05 4.68E+09 4.39E+09 l.07 62 43 l.371E-05 4.63E+09 4.35E+09 l.07 62 44 8.315E-06 4.58E+09 4.30E+09 1.07 62 45 5.043E-06 4.52E+09 4.24E+09 l.07 62 46 3.059E-06 4.43E+09 4.16E+09 l.07 62 47 l.855E-06 4.29E+09 4.03E+09 l.07 62 48 l.125E-06 4.03E+09 3.78E+09 l.07 62 49 6.826E-07 3.81E+09 3.57E+09 1.07 106 50 4.l40E-07 3.96E+09 3.7lE+09 l.07 106 51 2.5 l lE-07 l.07E+l0 l.OOE+lO l.07 106 52 l.523E-07 1.8 lE+lO l.70E+l0 1.07 106 53 9.237E-08 3.93E+l0 3.69E+l0 l.07 106 B-5
Table B-3 FERRET Spectrum Result - Palisades Cavity at l 6° Midplane, Cycle 8 Calculated and Adjusted Group Flux Results Group Energy (Me V) Calculated Flux Adjusted Flux Ratio Uncertainty (n/cm 2-s) (n/cm 2-s} Calci'.Adj Flux Percent lcr l.733E+Ol l.74E+05 l.36E+05 1.28 22 2 l.492E+Ol 4.17E+05 3.31E+05 1.26 19 3 l.350E+Ol l.70E+06 l.38E+06 1.24 16 4 1.162E+Ol 3.58E+06 2.96E+06 1.21 14 5 l.OOOE+Ol 7.73E+06 6.59E+06 1.17 11 6 8.607E+OO l.17E+07 l.04E+07 1.13 11 7 7.408E+OO 2.43E+07 2.26E+07 1.08 10 8 6.065E+OO 2.92E+07 2.83E+07 1.03 10 9 4.966E+OO 4.92E+07 4.93E+07 1.00 10 10 3.679E+OO 6.04E+07 6.17E+07 0.98 11 11 2.865E+OO l.30E+08 l.36E+08 0.96 11 12 2.231E+OO l.83E+08 l.93E+08 0.95 12 13 l.738E+OO 2.77E+08 2.93E+08 0.95 12 14 1.353E+OO 3.29E+08 3.46E+08 0.95 14 15 l.108E+OO 8.58E+08 8.92E+08 0.96 14 16 8.208E-Ol l.22E+09 1.24E+09 0.98 15 17 6.393E-Ol l.56E+09 l.56E+09 1.00 17 18 4.979E-Ol l.01E+09 9.93E+08 1.02 19 19 3.877E-01 2.10E+09 2.01E+09 1.05 21 20 3.020E-Ol 2.48E+09 2.31E+09 1.07 24 21 l.832E-Ol 2.66E+09 2.43E+09 1.09 25 22 l. l l lE-01 l.80E+09 l.61E+09 1.12 27 23 6.738E-02 l.37E+09 l.21E+09 1.14 29 I 24 4.087E-02 8.15E+08 7.02E+08 1.16 30 25 2.554E-Q2 l.51E+09 l.28E+09 1.18 31 26 l.989E-02 8.34E+08 6.96E+08 1.20 32 27 l.503E-02 8.02E+08 6.58E+08 1.22 32 28 9. l 19E-03 7.93E+08 6.38E+08 1.24 60 29 5.531E-03 7.82E+08 6.17E+08 1.27 60 B-6
Table B-3 (Continued)
FERRET Spectrum Result - Palisades Cavity at 16° Midplane, Cycle 8 Calculated and Adjusted Group Flux Results Group Energy (Me V) Calculated Flux Adjusted Flux Ratio Uncertainty (n/cm 2-s) (n/cm 2-s) CalcLAdj Flux Percent lcr 30 3.355E-03 2.4IE+08 l.86E+08 1.29 59 31 2.839E-03 2.26E+08 l.70E+08 1.33 59 32 2.404E-03 2. l6E+08 l.57E+08 1.38 59 33 2.035E-03 6.28E+08 4.35E+08 1.44 57 34 l.234E-03 6.12E+08 4.00E+08 1.53 56 35 7.485E-04 5.59E+08 3.43E+08 1.63 53 36 4.540E-04 4.97E+08 2.86E+08 L74 51 37 2.754E-04 5. l IE+08 2.78E+08 1.84 48 38 l.670E-04 5.19E+08 2.15E+08 2.41 17 39 l.013E-04 4.92E+08 2.60E+08 1.90 46 40 6.144E-05 4.70E+08 2.56E+08 1.83 48 41 3.727E-05 4.61E+08 2.62E+08 1.76 51 42 2.260E-05 4.48E+08 2.66E+08 1.69 53 43 l.371E-05 4.28E+08 2.63E+08 1.63 55 44 8.315E-06 4.05E+08 2.56E+08 1.58 56 45 5.043E-06 3.81E+08 2.45E+08 1.56 57 46 3.059E-06 3.59E+08 2.32E+08 1.54 57 47 l.855E-06 3.30E+08 2.16E+08 1.53 58 48 l.125E-06 2.74E+08 l.8 IE+08 1.52 58 49 6.826E~07 2.73E+08 l.35E+08 2.01 101 50 4.140E-07 4.32E+08 l.77E+08 2.44 95 51 2.511E-07 4.25E+08 l.48E+08 2.87 88 52 l.523E-07 4.18E+08 l.3 IE+08 3.19 82 53 9.237E-08 l.39E+09 3.0IE+08 4.60 52 B-7
Table B-4 FERRET Spectrum Result - Palisades Cavity at 26° Midplane, Cycle 8 Calculated and Adjusted Group Flux Results Group Energy (Me V) Calculated Flux Adjusted Flux Ratio Uncertainty (n/cm 2-s) {n/cm 2-s) Calc£'.Adj Flux Percent lcr l.733E+Ol l.45E+05 l.10E+05 1.31 22 2 l.492E+Ol 3.47E+05 2.69E+05 1.29 19 3 l.350E+Ol l.39E+06 l.10E+06 1.26 16 4 l.162E+Ol 2.86E+06 2.32E+06 1.23 14 5 l.OOOE+Ol 6.10E+06 5.l 1E+06 1.19 11 6 8.607E+OO 9. l 1E+06 7.97E+06 Ll4 11 7 7.408E+OO l.87E+07 l.72E+07 1.09 10 8 6.065E+OO 2.24E+07 2.13E+07 1.05 10 9 4.966E+OO 3.78E+07 3.71E+07 1.02 10 10 3.679E+OO 4.61E+07 4.60E+07 1.00 11 11 2.865E+OO l.01E+08 l.02E+08 0.99 11 12 2.231E+OO l.43E+08 l.45E+08 0.99 12 13 l.738E+OO 2.20E+08 2.22E+08 0.99 12 14 l.353E+OO 2.62E+08 2.60E+08 1.01 14 15 l.108E+OO 6.91E+08 6.70E+08 1.03 14 16 8.208E-Ol l.01E+09 9.51E+08 1.06 15 17 6.393E-Ol l.30E+09 l.20E+09 1.08 17 18 4.979E-Ol 8.76E+08 7.88E+08 1.11 19 19 3.877E-Ol l.76E+09 l.55E+09 l.14 21 20 3.020E-Ol 2.20E+09 l.89E+09 1.17 23 21 l.832E-Ol 2.36E+09 l.99E+09 l.19 25 22 l. l l lE-01 l.59E+09 l.32E+09 1.21 27 23 6.738E-02 l.23E+09 l.OOE+09 1.22 29 24 4.087E-02 7.33E+08 5.92E+08 1.24 30 25 2.554E-02 l.31E+09 l.05E+09 1.25 31 26 l.989E-02 7.42E+08 5.88E+08 1.26 32 27 l.503E-02 7.31E+08 5.75E+08 1.27 32 28 9. l 19E-03 7.26E+08 5.63E+08 1.29 60 29 5.531E-03 7.20E+08 5.51E+08 1.31 60 B-8
~~Table B-4 (Continued)~~
FERRET Spectrum Result - Palisades Cavity at 26° Midplane, Cycle 8 Calculated and Adjusted Group Flux Results Group Energy (Me V) Calculated Flux Adjusted Flux Ratio Uncertainty (n/cm 2-s) (n/cm 2-s) Calc£'.Adj Flux Percent lcr 30 3.355E-03 2.24E+08 1.69E+08 l.33 59 31 2.839E-03 2.08E+08 l.54E+08 l.35 59 32 2.404E-03 l.98E+08 l.42E+08 l.39 58 33 2.035E-03 5.77E+08 3.98E+08 l.45 57 34 l.234E-03 5.65E+08 3.71E+08 l.52 56 35 7.485E-04 5.16E+08 3.21E+08 l.61 53 36 4.540E-04 4.61E+08 2.71E+08 l.70 50 37 2.754E-04 4.68E+08 2.63E+08 l.78 48 38 l.670E-04 4.72E+08 2. l 1E+08 2.24 17 39 l.013E-04 4.53E+08 2.48E+08 l.83 46 40 6.144E-05 4.36E+08 2.45E+08 l.78 48 41 3.727E-05 4.27E+08 2.49E+08 l.72 51 42 2.260E-05 4. l4E+08 2.50E+08 l.66 53 43 l.371E-05 3.96E+08 2.47E+08 l.61 55 44 8.315E-06 3.75E+08 2.39E+08 l.57 56 45 5.043E-06 3.53E+08 2.28E+08 l.55 57 46 3.059E-06 3.32E+08 2.16E+08 l.54 58 47 1.855E-06 3.06E+08 2.00E+08 1.53 58 48 l.125E-06 2.55E+08 l.67E+08 1.53 58 49 6.826E-07 2.53E+08 l.24E+08 2.05 101 50 4.140E-07 4.00E+08 l.59E+08 2.51 95 51 2.5 l lE-07 3.94E+08 l.33E+08 2.97 89 52 l.523E-07 3.87E+08 l.17E+08 3.32 83 53 9.237E-08 l.29E+09 2.67E+08 4.83 54 B-9 I
L
Table B-5 FERRET Spectrum Result - Palisades Cavity at 26° Bottom, Cycle 8 Calculated and Adjusted Group Flux Results Group Energy (Me V) Calculated Flux Adjusted Flux Ratio Uncertainty (n/cm 2-s) {n/cm 2-s2 CalcLAdj Flux Percent la l.733E+Ol 4.34E+04 3.06E+04 1.42 22 2 l.492E+Ol l.04E+05 7.34E+04 1.42 19 3 1.350E+Ol 4.18E+05 2.99E+05 1.40 16 4 1.162E+Ol 8.57E+05 6.26E+05 1.37 14 5 l.OOOE+Ol l.83E+06 l.39E+06 1.32 11 6 8.607E+OO 2.73E+06 2.22E+06 1.23 11 7 7.408E+OO 5.62E+06 4.9 IE+06 Ll4 10 8 6.065E+OO 6.71E+06 . 6.35E+06 1.06 10 9 4.966E+OO l.13E+07 l.15E+07 0.98 10 10 3.679E+OO l.38E+07 l.48E+07 0.94 10 11 2.865E+OO 3.02E+07 3.41E+07 0.89 11 12 2.231E+OO 4.28E+07 5.03E+07 0.85 11 13 l.738E+OO 6.60E+07 7.95E+07 0.83 12 14 l.353E+OO 7.86E+07 9.49E+07 0.83 14 15 1.108E+OO 2.07E+08 2.50E+08 0.83 14 16 8.208E-Ol 3.02E+08 3.57E+08 0.84 15 17 6.393E-01 3.89E+08 4.51E+08 0.86 17 18 4.979E-Ol 2.63E+08 2.96E+08 0.89 19 19 3.877E-Ol 5.29E+08 5.79E+08 0.91 21 20 3.020E-01 6.59E+08 6.99E+08 0.94 23 21 1.832E-01 7.08E+08 7.31E+08 0.97 25 22 1.11 lE-O l 4.77E+08 4.80E+08 0.99 27 23 6.738E-02 3.67E+08 3.62E+08 1.02 29 24 4.087E-02 2.20E+08 2.13E+08 1.03 30 25 2.554E-02 3.93E+08 3.75E+08 1.05 31 26 l.989E-02 2.22E+08 2.10E+08 1.06 32 27 l.503E-02 2.19E+08 2.05E+08 1.07 32 28 9. l 19E-03 2.18E+08 2.03E+08 1.07 60 29 5.531E-03 2.16E+08 2.01E+08 1.08 60 B-10
Table B-5 (Continued)
FERRET Spectrum Result - Palisades Cavity at 26° Bottom, Cycle 8 Calculated and Adjusted Group Flux Results Group Energy (MeV) Calculated Flux Adjusted Flux Ratio Uncertainty (n/cm 2 -s) (n/cm 2-s} CalcLAdj Flux Percent lcr 30 3.355E-03 6.71E+07 6.22E+07 1.08 59 31 2.839E-03 6.24E+07 5.78E+07 1.08 59 32 2.404E-03 5.94E+07 5.50E+07 1.08 59 33 2.035E-03 l.73E+08 l.60E+08 1.08 57 34 l.234E-03 l.70E+08 l.57E+08 1.08 56 I 35 7.485E-04 l.55E+08 l.44E+08 1.08 53 36 4.540E-04 l.38E+08 l.28E+08 1.08 50 37 2.754E-04 l.40E+08 l.30E+08 1.08 48 38 l.670E-04 l.42E+08 l.32E+08 1.07 15 39 l.013E-04 l.36E+08 l.26E+08 1.08 47 40 6.l44E-05 1.31E+08 l.20E+08 1.09 49 .I 41 3.727E-05 l.28E+08 l. l7E+08 1.09 52 42 2.260E-05 l.24E+08 l.13E+08 1.10 54 43 l.371E-05 l. l9E+08 l.07E+08 l.l l 56 44 8.3 l5E-06 l. l3E+08 l.OlE+08 1.12 57 45 5.043E-06 l.06E+08 9.40E+07 1.13 58 46 3.059E-06 9.97E+07 8.77E+07 1.14 58 47 l.855E-06 9.l9E+07 8.0lE+07 1.15 59 48 1. l25E-06 7.64E+07 6.60E+07 l.16 59 49 6.826E-07 7.59E+07 5.48E+07 1.38 101 50 4.l40E-07 l.20E+08 7.51E+07 1.60 97 51 2.51 lE-07 l. l8E+08 6.53E+07 1.8 l 90 52 l.523E-07 l. l6E+08 5.89E+07 l.97 84 53 9.237E-08 3.86E+08 l.50E+08 2.58 54 B-11
Table B-6 FERRET Spectrum Result - Palisades Cavity at 39° Midplane, Cycle 8 Calculated and Adjusted Group Flux Results Group Energy (MeV) Calculated Flux Adjusted Flux Ratio Uncertainty (n/cm 2-s) (n/cm 2-s} Calc[Adj Flux Percent lcr l.733E+Ol 1.13E+05 8.71E+04 1.29 22 2 l.492E+Ol 2.71E+05 2.12E+05 1.28 19 3 l.350E+Ol l.07E+06 8.56E+05 1.25 16 4 l.162E+Ol 2.14E+06 l.74E+06 1.23 14 5 l.OOOE+Ol 4.52E+06 3.79E+06 1.19 11 6 8.607E+OO 6.64E+06 5.78E+06 1.15 11 7 7.408E+OO l.36E+07 l.22E+07 1.11 10 8 6.065E+OO l.62E+07 l.51E+07 1.07 10 9 4.966E+OO 2.74E+07 2.61E+07 1.05 10 10 3.679E+OO 3.38E+07 3.24E+07 1.04 11 11 2.865E+OO 7.36E+07 7.07E+07 1.04 11 12 2.231E+OO l.04E+08 9.89E+07 1.05 12 13 l.738E+OO l.64E+08 l.54E+08 1.06 12 14 l.353E+OO l.93E+08 l.79E+08 1.08 14 15 l.108E+OO 5.17E+08 4.71E+08 1.10 14 16 8.208E-Ol 7.67E+08 6.83E+08 1.12 15 17 6.393E-01 l.02E+09 8.93E+08 1.15 17 18 4.979E-Ol 7.14E+08 6~10E+08 1.17 19 19 3.877E-Ol l.41E+09 l.18E+09 1.19 21 20 3.020E-Ol l.89E+09 l.56E+09 1.21 23 21 l.832E-Ol 2.02E+09 l.65E+09 1.22 25 22 l.lllE-01 l.40E+09 l.13E+09 1.24 27 23 6.738E-02 l.09E+09 8.77E+08 1.25 29 24 4.087E-02 6.63E+08 5.29E+08 1.25 30 25 2.554E-02 l.10E+09 8.69E+08 1.26 31 26 l.989E-02 6.55E+08 5.16E+08 1.27 32 27 l.503E-02 6.81E+08 5.33E+08 1.28 32 28 9. l 19E-03 6.78E+08 5.24E+08 1.29 59 29 5.53 lE-03 6.74E+08 5.15E+08 1.31 59 B-12
~~Table B-6 (Continued)~~
FERRET Spectrum Result - Palisades Cavity at 39° Midplane, Cycle 8 Calculated and Adjusted Group Flux Results Group Energy (MeV) Calculated Flux Adjusted Flux Ratio Uncertainty 2
(n/cm 2-s) (n/cm -s~ Calc[Adj Flux Percent lcr 30 3.355E-03 2. l IE+08 l.59E+08 1.33 59 31 2.839E-03 l.97E+08 l.45E+08 1.35 59 32 2.404E-03 l.87E+08 l.34E+08 1.39 58 33 2.035E-03 5.44E+08 3.76E+08 1.45 57 34 l.234E-03 5.33E+08 3.52E+08 1.52 56 35 7.485E-04 4.91E+08 3.07E+08 1.60 53 36 4.540E-04 4.39E+08 2.61E+08 1.68 50 37 2.754E-04 4.50E+08 2.56E+08 1.76 48 38 l.670E-04 4.57E+08 2.08E+08 2.20 17 39 l.013E-04 4.34E+08 2.41E+08 1.80 46 40 6.144E-05 4.14E+08 2.36E+08 1.75 48 41 3.727E-05 4.06E+08 2.40E+08 1.69 51 42 2.260E-05 3.95E+08 2.43E+08 1.63 53 43 1.37 lE-05 3.78E+08 2.40E+08 1.58 55 44 8.315E-06 3.58E+08 2.33E+08 1.54 56 45 5.043E-06 3.38E+08 2.23E+08 1.52 57 46 3.059E-06 3.18E+08 2.12E+08 1.50 58 47 l.855E-06 2.93E+08 l.97E+08 1.49 58 48 l.125E-06 2.44E+08 l.65E+08 1.48 58 49 6.826E-07 2.43E+08 l.35E+08 1.80 101 50 4.140E-07 3.83E+08 l.85E+08 2.06 96 51 2.5 l lE-07 3.76E+08 l.62E+08 2.33 89 52 l.523E-07 3.71E+08 l.46E+08 2.54 82 53 9.237E-08 l.23E+09 3.63E+08 3.40 47 B-13
Table B-7 FERRET Spectrum Result - Palisades Cavity at 6° Midplane, Cycle 8-9 Calculated and Adjusted Group Flux Results Group Energy (Me V) Calculated Flux Adjusted Flux Ratio Uncertainty (n/cm 2-s) (n/cm 2-s} Calci'.Adj Flux Percent lcr l.733E+Ol l.45E+05 l.15E+05 0.79 22 2 1.492E+Ol 3.46E+05 2.80E+05 0.81 19 3 l.350E+Ol l.37E+06 l.14E+06 0.83 16 4 l.162E+Ol 2.77E+06 2.36E+06 0.85 . 14 5 l.OOOE+Ol 5.89E+06 5.18E+06 0.88 11 6 8.607E+OO 8.73E+06 8.0lE+06 0.92 11 7 7.408E+OO 1.78E+07 l.70E+07 0.96 10 8 6.065E+OO 2.lOE+07 2.08E+07 0.99 10 9 4.966E+OO 3.49E+07 3.53E+07 1.0 l 10 10 3.679E+OO 4.27E+07 4.34E+07 1.02 11 11 2.865E+OO 9.19E+07 9.31E+07 1.0 l 11 12 2.231E+OO l.30E+08 l.30E+08 1.00 12 13 l.738E+OO 2.00E+08 l.96E+08 0.98 12 14 l.353E+OO 2.38E+08 2.29E+08 0.96 14 15 l.108E+OO 6.27E+08
5.86E+08 0.93 14 16 8.208E-Ol 9. l lE+08 8.28E+08 0.91 16 17 6.393E-Ol l.17E+09 l.04E+09 0.89 17 18 4.979E-Ol 7.84E+08 6.78E+08 0.86 20 19 3.877E-Ol l.60E+09 l.35E+09 0.85 21 20 3.020E-Ol l.96E+09 l.63E+09 0.83 24 21 l.832E-Ol 2.12E+09 l.74E+09 0.82 25 22 1.11 lE-O l l.44E+09 l.17E+09 0.81 27 23 6.738E-02 l. l lE+09 8.93E+08 0.81 29 24 4.087E-02 6.74E+08 5.40E+08 0.80 30 25 2.554E-02 l.19E+09 9.48E+08 0.80 31 26 l.989E-02 6.76E+08 5.35E+08 0.79 32 27 l.503E-02 6.67E+08 5.25E+08 0.79 32
~~28 29~~
~~9. l 19E-03 5.531E-03 6.61E+08 6.53E+08 5.14E+08 5.02E+08 0.78 0.77 60 60 B-14~~
~~Table B-7 (Continued)~~
FERRET Spectrum Result - Palisades Cavity at 6° Midplane, Cycle 8-9 Calculated and Adjusted Group Flux Results Group Energy (Me V) Calculated Flux Adjusted Flux Ratio Uncertainty (n/cm 2 -s) (n/cm 2-s2 Calc£'.Adj Flux Percent lcr 30 3.355E-03 2.02E+08 l.53E+08 0.76 59 31 2.839E-03 l.89E+08 l.40E+08 0.74 59 32 2.404E-03 l.80E+08 l.30E+08 0.72 58 33 2.035E-03 5.24E+08 3.63E+08 0.69 57 34 l.234E-03 5.12E+08 3.37E+08 0.66 56 35 7.485E-04 4.69E+08 2.92E+08 0.62 53 36 4.540E-04 4.17E+08 2.46E+08 0.59 50 37 2.754E-04 4.28E+08 2.41E+08 0.56 48 38 l.670E-04 4.35E+08 l.93E+08 0.44 17 39 l.013E-04 4.12E+08 2.26E+08 0.55 46 40 6.144E-05 3.93E+08 2.22E+08 0.56 48 41 3.727E-05 3.86E+08 2.26E+08 0.59 51 42 2.260E-05 3.75E+08 2.28E+08 0.61 53 43 l.371E-05 3.58E+08 2.26E+08 0.63 55 44 8.315E-06 3.39E+08 2.19E+08 0.65 56 45 5.043E-06 3.19E+08 2.09E+08 0.66 57 46 3.059E-06 3.00E+08 I.99E+08 0.66 58 47 l.855E-06 2.77E+08 I.85.E+08 0.67 58 48 1.125E-06 2.30E+08 l.55E+08 0.67 58 49 6.826E-07 2.29E+08 I.22E+08 0.53 101 50 4.140E-07 3.61E+08 I.64E+08 0.45 95 51 2.51 lE-07 3.54E+08 I.40E+08 0.39 89 52 I.523E-07 3.47E+08 l.25E+08 0.36 82 53 9.237E-08 l.18E+09 3.04E+08 0.26 49 B-15
Table B-8 FERRET Spectrum Result - Palisades Cavity at 6° Bottom, Cycle 8-9 Calculated and Adjusted Group Flux Results Group Energy (Me V) Calculated Flux Adjusted Flux Ratio Uncertainty (n/cm 2 -s) (n/cm 2-s2 CalcLAdj Flux Percent lcr l.733E+Ol 2.54E+04 l.91E+04 0.75 22 2 l.492E+Ol 6.06E+04 4.53E+04 0.75 19 3 l.350E+Ol 2.40E+05 l.80E+05 0.75 16 4 l.162E+OI 4.86E+05 3.67E+05 0.76 14 5 1.000E+Ol l.03E+06 8.03E+05 0.78 11 6 8.607E+OO l.53E+06 l.26E+06 0.83 11 7 7.408E+OO 3.12E+06 2.76E+06 0.88 IO 8 6.065E+OO 3.68E+06 3.52E+06 0.96 10 9 4.966E+OO 6.11E+06 6.30E+06 l.03 IO 10 3.679E+OO 7.47E+06 8.16E+06 l.09 10
I 11 12 13 14 2.865E+OO 2.231E+OO 1.738E+OO l.353E+OO l.61E+07 2.28E+07 3.50E+07 4.17E+07 l.86E+07 2.75E+07 4.41E+07 5.45E+07 l.16 1.21 l.26 1.31 11 11 12 14 15 l.108E+OO l.10E+08 l.47E+08 1.34 14 16 8.208E-Ol l.60E+08 2.15E+08 1.35 15 17 6.393E-Ol 2.05E+08 2.77E+08 1.35 17 18 4.979E-Ol l.37E+08 l.82E+08 l.33 19 19 3.877E-Ol 2.80E+08 3.66E+08 1.31 21 20 3.020E-01 3.44E+08 4.40E+08 l.28 23 21 1.832E-O 1 3.70E+08 4.63E+08 1.25 25 22 1.11lE-O1 2.52E+08 3.08E+08 l.22 27 23 6.738E-02 l.94E+08 2.31E+08 1.19 29 24 4.087E-02 l.18E+08 l.38E+08 1.17 30 25 2.554E-0-2 2.08E+08 2.39E+08 1.15 31 26 l.989E-02 l.18E+08 l.34E+08 1.13 32 27 l.503E-02 l.17E+08 l.30E+08 1.12 32 28 9. l 19E-03 l.16E+08 l.29E+08 1.11 60 29 5.531E-03 1.14E+08 l.27E+08 1.11 60 B-16
~~Table B-8 (Continued)~~
FERRET Spectrum Result - Palisades Cavity at 6° Bottom, Cycle 8-9 Calculated and Adjusted Group Flux Results Group Energy (MeV) Calculated Flux Adjusted Flux Ratio Uncertainty (n/cm 2-s) {n/cm 2-s} Calc£'.Adj Flux Percent lcr 30 3.355E-03 3.54E+07 3.93E+07 I.I I 59 31 2.839E-03 3.31E+07 3.69E+07 1.12 59 32 2.404E-03 3.15E+07 3.57E+07 1.13 59 33 2.035E-03 9.17E+07 l.06E+08 1.16 57 34 l.234E-03 8.96E+07 l.07E+08 1.19 56 35 7.485E-04 8.20E+07 l.OIE+08 1.23 53 36 4.540E-04 7.3 IE+07 9.27E+07 1.27 50 37 2.754E-04 7.49E+07 9.77E+07 1.30 48 38 l.670E-04 7.61E+07 l.13E+08 1.49 14 39 l.013E-04 7.21E+07 9.41E+07 1.30 47 40 6.144E-05 6.89E+07 8.86E+07 1.29 49 41 3.727E-05 6.75E+07 8.38E+07 1.24 52 42 2.260E-05 6.56E+07 7.86E+07 1.20 54 43 1.371E-05 6.28E+07 7.29E+07 1.16 56 44 8.315E-06 5.94E+07 6.71E+07 1.13 . 57 45 5.043E-06 5.59E+07 6.19E+07 1.11 58 46 3.059E-06 5.26E+07 5.72E+07 1.09 59 47 l.855E-06 4.85E+07 5.19E+07 1.07 59 48 l.125E-06 4.03E+07 4.26E+07 1.06 59 49 6.826E-07 4.00E+07 3.93E+Q7 0.98 102 50 4.140E-07 6.32E+07 5.78E+07 0.92 98 51 2.511E-07 6.19E+07 5.32E+07 0.86 91 52 l.523E-07 6.08E+07 4.98E+07 0.82 85 53 9.237E-08 2.06E+08 l.48E+08 0.72 48 B-17
Table B-9 FERRET Spectrum Result - Palisades Cavity at 16° Midplane, Cycle 9 Calculated and Adjusted Group Flux Results Group Energy (Me V) Calculated Flux Adjusted Flux Ratio Uncertainty (n/cm 2 -s) (n/cm 2 -s2 Calc£'.Adj Flux Percent lcr l.733E+Ol l.41E+05 l. lOE+05 l.28 22 2 l.492E+Ol 3.35E+05 2.67E+05 l.25 19 3 l.350E+Ol l.32E+06 l.08E+06 l.23 16 4 1.162E+Ol 2.68E+06 2.24E+06 1.20 14 5 l.OOOE+Ol 5.70E+06 4.89E+06 1.16 11 6 8.607E+OO 8.45E+06 7.55E+06 1.12 11 7 7.408E+OO l.73E+07 l.61E+07 l.08 10 8 6.065E+OO 2.05E+07 l.96E+07 l.04 10 9 4.966E+OO 3.39E+07 3.31E+07 l.02 10 10 3.679E+OO 4.13E+07 4.01E+07 1.03 11 11 2.865E+OO 8.87E+07 8.53E+07 1.04 11 12 2.231E+OO 1.25E+08 l. l 7E+08 l.06 12 13 l.738E+OO 1.89E+08 l.75E+08 1.08 12 14 l.353E+OO 2.25E+08 2.07E+08 1.09 14 15 l.108E+OO 5.88E+08 5.31E+08 1.11 14 16 8.208E-Ol 8.40E+08 7.46E+08 1.13 16 17 6.393E-Ol l.08E+09 9.39E+08 1.15 17 18 4.979E-Ol 7.09E+08 6.08E+08 1.17 20 19 3.877E-Ol 1.46E+09 l.23E+09 1.18 21 .
20 3.020E-Ol l.75E+09 l.46E+09 1.19 24 21 1.832E-Ol l.88E+09 l.56E+09 1.20 25 22 1.11 lE-Ol 1.25E+09 l.03E+09 1.21 27 23 6.738E-02 9.57E+08 7.84E+08 1.22 29 24 4.087E-02 5.68E+08 4.62E+08 1.23 30 25 2.554E-02 l.05E+09 8.49E+08 1.24 31 26 l.989E-02 5.82E+08 4.67E+08 1.25 32 27 l.503E-02 5.59E+08 4.44E+08 1.26 32 28 9.l 19E-03 5.53E+08 4.34E+08 1.27 60 29 5.531E-03 5.45E+08 4.22E+08 1.29 60 B-18
Table B-9 (Continued)
FERRET Spectrum Result - Palisades Cavity at 16° Mid plane, Cycle 9 Calculated and Adjusted Group Flux Results Group Energy (Me V) Calculated Flux Adjusted Flux Ratio Uncertainty (n/cm 2 -s) (n/cm 2-s} Calc[Adj Flux Percent lcr 30 3.355E-03 l.68E+08 l.28E+08 1.31 59 31 2.839E-03 l.57E+08 l. l 7E+08 1.34 59 32 2.404E-03 l.51E+08 l.09E+08 1.38 59 33 2.035E-03 4.38E+08 3.05E+08 1.44 57 34 l.234E-03 4.26E+08 2.83E+08 1.51 56 35 7.485E-04 3.90E+08 2.45E+08 1.59 53 36 4.540E-04 3.47E+08 2.07E+08 1.67 50 37 2.754E-04 3.56E+08 2.04E+08 1.75 48 38 l.670E-04 3.62E+08 l.65E+08 2.19 17 39 l.013E-04 3.43E+08 l.91E+08 1.79 46 40 6.144E-05 3.27E+08 l.88E+08 1.74 49 41 3.727E-05 3.21E+08 l.91E+08 1.69 51 42 2.260E-05 3.12E+08 1.92E+08 1.63 53 43 l.371E-05 2.99E+08 l.89E+08 1.58 -55 44 8.315E-06 2.82E+08 l.83E+08 1.55 56 45 5.043E-06 2.66E+08 l.74E+08 1.53 57 46 3.059E-06 2.50E+08 l.65E+08 1.52 58 47 l.855E-06 2.30E+08 l.53E+08 1.51 58 48 l.125E-06 l.91E+08 l.28E+08 1.50 58 49 6.826E-07 1.90E+08 9.81E+07 1.94 101 50 4.140E-07 3.00E+08 l.30E+08 2.32 95 51 2.51 lE-07 2.94E+08 l.09E+08 2.69 89 52 l.523E-07 2.88E+08 9.64E+07 2.98 83 53 9.237E-08 9.73E+08 2.30E+08 4.24 52 B-19
1-Table B-10 FERRET Spectrum Result - Palisades Cavity at 26° Midplane, Cycle 9 Calculated and Adjusted Group Flux Results Group Energy (MeV) Calculated Flux Adjusted Flux Ratio Uncertainty (n/cm 2-s) {n/cm 2-s} Calc£'.Adj Flux Percent lcr l.733E+Ol l.18E+05 9.24E+04 1.28 22 2 l.492E+Ol 2.86E+05 2.27E+05 1.26 19 3 l.350E+Ol l.14E+06 9.30E+05 1.23 16 4 1.162E+Ol 2.28E+06 l.90E+06 1.20 14 5 l.OOOE+Ol 4.85E+06 4.16E+06 1.16 11 I 6 8.607E+OO 7.14E+06 6.38E+06 1.12 11 7 7.408E+OO 1.46E+07 l.35E+07 1.08 10 8 6.065E+OO l.72E+07 l.65E+07 1.04 10 9 4.966E+OO 2.85E+07 2.79E+07 1.02 10 10 3.679E+OO 3.49E+07 3.42E+07 1.02 11 11 2.865E+OO 7.50E+07 7.35E+07 1.02 11 12 2.231E+OO l.06E+08 l.02E+08 1.03 12 13 1.738E+OO l.62E+08 l.55E+08 1.05 12 14 l.353E+OO l.93E+08 l.81E+08 1.06 14 15 l.108E+OO 5.07E+08 4.65E+08 1.09 14 16 8.208E-Ol 7.35E+08 6.60E+08 1.11 16 17 6.393E-Ol 9.48E+08 8.31E+08 1.14 17 18 4.979E-Ol 6.40E+08 5.49E+08 1.16 19 19 3.877E-Ol l.29E+09 l.08E+09 1.19 21 20 3.020E-Ol l.60E+09 l.33E+09 1.21 23 21 1.832E-Ol l.72E+09 1.41E+09 1.22 25 22 1.11 lE-Ol l.16E+09 9.40E+08 1.23 27 23 6.738E-02 8.94E+08 7.18E+08 1.24 29 24 4.087E-02 5.35E+08 4.27E+08 1.25 30 25 2.554E-02 9.57E+08 7.59E+08 1.26 31 26 1.989E-02 5.41E+08 4.27E+08 1.27 32 27 l.503E-02 5.33E+08 4.17E+08 1.28 32 28 9.119E-03 5.30E+08 4.10E+08 1.29 60 29 5.531E-03 5.25E+08 4.01E+08 1.31 60 B-20
___J
Table B-10 (Continued)
FERRET Spectrum 'Result - Palisades Cavity at 26° Midplane, Cycle 9 Calculated and Adjusted Group Flux Results Group Energy (Me V) Calculated Flux Adjusted Flux Ratio Uncertainty (n/cm 2-s) (n/cm 2-s2 Calc[Adj Flux Percent lcr 30 3.355E-03 l.63E+08 l.23E+08 l.33 59 31 2.839E-03 l.52E+08 l.l2E+08 l.35 59 32 2.404E-03 l.44E+08 l.04E+08 l.39 58 33 2.035E-03 4.21E+08 2.91E+08 1.44 57 34 l.234E-03 4.13E+08 2.73E+08 1.51 56 35 7.485E-04 3.76E+08 2.36E+08 1.59 53 36 4.540E-04 3.36E+08 2.0IE+08 l.68 50 37 2.754E-04 3.42E+08 l.95E+08 l.75 48 38 l.670E-04 3.45E+08 l.58E+08 2.18 17 39 l.013E-04 3.31E+08 l.84E+08 1.80 46 40 6.l44E-05 3.18E+08 l.82E+08 l.75 48 41 3.727E-05 3.l2E+08 l.84E+08 l.70 51 42 2.260E-05 3.02E+08 1.84E+08 1.64 53 43 l.371E-05 2.89E+08 l.81E+08 1.59 55 44 8.315E-06 2.74E+08 1.75E+08 l.57 56 45 5.043E-06 2.58E+08 l.67E+08 l.55 57 46 3.059E-06 2.43E+08 l.57E+08 1.54 58 47 l.855E-06 2.24E+08 l.46E+08 1.54 58 48 l.125E-06 1.86E+08 1.21E+08 1.53 58 49 6.826E-07 1.85E+08 8.85E+07 2.09 101 50 4.140E-07 2.91E+08 1.12E+08 2.59 95 51 2.51 lE-07 2.85E+08 9.22E+07 3.09 89 52 l.523E-07 2.79E+08 8.04E+07 3.47 83 53 9.237E-08 9.46E+08 l.84E+08 5.16 56 B-21
Table B-11 FERRET Spectrum Result - Palisades Cavity at 26° Bottom, Cycle 9 Calculated and Adjusted Group Flux Results Group Energy (MeV) Calculated Flux Adjusted Flux Ratio Uncertainty (n/cm 2-s) ~n/cm -s}
2 CalcLAdj Flux Percent lcr l.733E+Ol 3.6IE+04 2.75E+04 0.76 22 2 l.492E+Ol 8.72E+04 6.67E+04 0.76 19 3 l.350E+Ol 3.49E+05 2.69E+05 0.77 16 4 l.162E+Ol 6.96E+05 5.45E+05 0.78 14 5 1.000E+Ol 1.48E+06 1.19E+06 0.80 11 6 8.607E+OO 2.18E+06 1.84E+06 0.84 11 7 7.408E+OO 4.45E+06 3.95E+06 0.89 10 8 6.065E+OO 5.25E+06 4.92E+06 0.94 10 9 4.966E+OO 8.71E+06 8.54E+06 0.98 10 10 3.679E+OO 1.06E+07 1.07E+07 1.00 11 11 2.865E+OO 2.29E+07 2.35E+07 1.03 11 12 2.231E+OO 3.22E+07 3.35E+07 1.04 12 13 1.738E+OO 4.96E+07 5.24E+07 1.06 12 14 1.353E+OO 5.89E+07 6.40E+07 1.09 14 15 1.l08E+OO 1.55E+08 l.70E+08 l.10 14 16 8.208E-01 2.25E+08 2.48E+08 1.10 15 17 6.393E-01 2.89E+08 3.18E+08 1.10 17 18 4.979E-01 l.95E+08 2.13E+08 1.09 19 19 3.877E-01 3.93E+08 4.24E+08 1.08 21 20 3.020E-01 4.89E+08 5.22E+08 1.07 23 21 l.832E-Ol 5.26E+08 5.53E+08 1.05 25 22 l.11 lE-01 3.54E+08 3.67E+08 1.04 27 23 6.738E-02 2.73E+08 2.79E+08 1.02 29 24 4.087E-02 1.63E+08 1.64E+08 1.01 30 25 2.554E-02 2.92E+08 2.90E+08 0.99 31 26 1.989E-02 1.65E+08 1.62E+08 0.98 32 27 l.503E-02 1.63E+08 1.58E+08 0.97 32 28 9.119E-03 l.62E+08 1.55E+08 0.96 60 29 5.531E-03 l.60E+08 1.53E+08 0.95 60 B-22
Table B-11 (Continued)
FERRET Spectrum Result - Palisades Cavity at 26° Bottom, Cycle 9 Calculated and Adjusted Group Flux Results Group Energy (Me V) Calculated Flux Adjusted Flux Ratio Uncertainty (n/cm 2-s) (n/cm 2-s2 CalcLAdj Flux .Percent l cr 30 3.355E-03 4.98E+07 4.71E+07 0.95 59 31 2.839E-03 4.63E+07 4.36E+07 0.94 59 32 2.404E-03 4.41E+07 4.13E+07 0.94 59 33 2.035E-03 l.29E+08 l.20E+08 0.93 57 34 l.234E-03 l.26E+08 l.17E+08 0.93 56 35 7.485E-04 l.15E+08 l.07E+08 0.93 53 36 4.540E-04 l.03E+08 9.52E+07 0.93 50 37 2.754E-04 l.04E+08 9.67E+07 0.93 48 38 l.670E-04 l.05E+08 9.62E+07 0.91 15 39 l.013E-04 l.01E+08 9.28E+07 0.92 47
40 6.144E-05 9.72E+07 8.98E+07 0.92 49 41 3.727E-05 9.51E+07 8.71E+07 0.92 52 42 2.260E-05 9.22E+07 8.38E+07 0.91 54 43 l.371E-05 8.82E+07 7.97E+07 0.90 56 44 8.315E-06 8.36E+07 7.48E+07 0.90 57 45 5.043E-06 7.87E+07 6.98E+07 0.89 58 46 3.059E-06 7.40E+07 6.50E+07 0.88 58 47 l.855E-06 6.82E+07 5.94E+07 0.87 59 48 l.125E-06 5.68E+07 4.89E+07 0.86 59 49 6.826E-07 5.64E+07 4.02E+07 0.71 101 50 4.140E-07 8.88E+07 5.45E+07 0.61 97 51 2.51 lE-07 8.70E+07 4.69E+07 0.54 90 52 l.523E-07 8.53E+07 4.20E+07 0.49 84 53 9.237E-08 2.89E+08 l.07E+08 0.37 54 B-23
Table B-12 FERRET Spectrum Result - Palisades Cavity at 39° Midplane, Cycle 9 Calculated and Adjusted Group Flux Results Group Energy (MeV) Calculated Flux Adjusted Flux Ratio Uncertainty
~n/cm -s2 2
(n/cm 2-s) CalcLAdj Flux Percent l cr l.733E+Ol 9.06E+04 6.95E+04 1.30 22 2 l.492E+Ol 2. l6E+05 l.69E+05 1.28 19 3 l.350E+Ol 8.37E+05 6.69E+05 1.25 16 4 l.l62E+Ol l.64E+06 l.34E+06 1.22 13 5 l.OOOE+Ol 3.45E+06 2.89E+06 1.19 11 6 8.607E+OO 5.05E+06 4.38E+06 1.15 11 7 7.408E+OO l.03E+07 9.21E+06 1.12 10 8 6.065E+OO 1.23E+07 l.13E+07 1.09 10 9 4.966E+OO 2.07E+07 l.92E+07 1.08 10 10 3.679E+OO 2.55E+07 2.34E+07 1.09 11 11 2.865E+OO 5.53E+07 5.00E+07 1.11 11 12 2.231E+OO 7.78E+07 6.85E+07 l.14 12 13 l.738E+OO l.22E+08 l.05E+08 1.16 13 14 l.353E+OO l.44E+08 l.22E+08 1.18 14 15 l.l08E+OO 3.86E+08 3.17E+08 1.22 15 16 8.208E-Ol 5.71E+08 4.58E+08 1.25 16 17 6.393E-Ol 7.60E+08 5.97E+08 1.27 17 18 4.979E-Ol 5.28E+08 4.09E+08 1.29 19 19 3.877E-Ol l.04E+09 7.96E+08 l.31 21 20 3.020E-Ol l.39E+09 l.05E+09 1.32 23 21 l.832E-Ol l.49E+09 l.13E+09 1.32 25 22 1. l llE-01 l.03E+09 7.77E+08 1.33 27 23 6.738E-02 8.06E+08 6.08E+08 1.33 29 24 4.087E-02 4.89E+08 3.69E+08 1.32 30 25 2.554E-02 8.09E+08 6.l lE+08 1.32 31 26 l.989E-02 4.83E+08 3.65E+08 1.32 32 27 l.503E-02 5.02E+08 3.79E+08 1.33 32
~~28 29~~
~~9. l 19E-03 5.531E-03 5.00E+08 4.97E+08 3.74E+08 3.69E+08 l.34 l.35 59 59 B-24~~
~~Table B-12 (Continued)~~
FERRET Spectrum Result - Palisades Cavity at 39° Midplane, Cycle 9 Calculated and Adjusted Group Flux Results Group Energy (Me V) Calculated Flux Adjusted Flux Ratio Uncertainty (n/cm2 -s) (n/cm 2-s2 CalcLAdj Flux Percent lcr 30 3.355E-03 l.56E+08 l.14E+08 1.36 59 31 2.839E-03 l.45E+08 l.05E+08 1.39 59 32 2.404E-03 l.38E+08 9.71E+07 1.42 58 33 2.035E-03 4.02E+08 2.73E+08 1.47 57 34 l.234E-03 3.93E+08 2.56E+08 1.53 56 35 7.485E-04 3.62E+08 2.25E+08 1.61 53 36 4.540E-04 3.24E+08 l.92E+08 1.69 50 37 2.754E-04 3.32E+08 l.90E+08 1.75 48 38 l.670E-04 3.37E+08 l.58E+08 2.14 17 39 l.013E-04 3.20E+08 l.79E+08 1.79 46 40 6.144E-05 3.06E+08 l.75E+08 1.75 49 41 3.727E-05 3.00E+08 l.77E+08 1.69 51 42 2.260E-05 2.91E+08 l.78E+08 1.63 53
~*. 43 l.371E-05 2.79E+08 l.76E+08 1.59 55 44 8.315E-06 2.64E+08 l.70E+08 1.56 56 45 5.043E-06 2.49E+08 l.62E+08 1.54 57 46 3.059E-06 2.35E+08 l.54E+08 1.53 58 47 l.855E-06 2.16E+08 l.43E+08 1.52 58 48 1.125E-06 l.80E+08 l.20E+08 1.51 58 49 6.826E-07 1.79E+08 9.59E+07 1.87 101 50 4. l40E-07 2.8 IE+08 l.30E+08 2.17 96 51 2.5 l lE-07 2.76E+08 l.12E+08 2.47 89 52 l.523E-07 2.70E+08 9.99E+07 2.71 83 53 9.237E-08 9.17E+08 2.48E+08 3.70 49 B-25 L

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