ML20003B149
| ML20003B149 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 12/15/1980 |
| From: | Farmelo D, Fromm E, Perrin J Battelle Memorial Institute, COLUMBUS LABORATORIES |
| To: | |
| Shared Package | |
| ML20003B148 | List: |
| References | |
| NUDOCS 8102100451 | |
| Download: ML20003B149 (155) | |
Text
{{#Wiki_filter:. . - __ O I FINAL REPORT I on I I CALVERT CLIFFS UNIT N0. 1 NUCLEAR PLANT REACTOR PRESSURE VESSEL SURVEILLANCE I PROGRAM: CAPSULE 263 to BALTIM0RE GAS AND ELECTRIC COMPANY I December 15,1980 by J. S. Perrin, E. O. Fromm, D. R. Farmelo, R. S. Denning, and R. G. Jung I BATTELLE I Columbus Laboratories 501 King Avenue Columbus, Ohio 43201 Battelle is not engaged in research for advertising, sales promotion, or publi,ity purposes, and this report may not be reproduced in full or in I part for such purposes. 01/ o O Vh I.
I I ' I TABLE OF CONTENTS Pace
SUMMARY
.............................. 1 INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 CAPSULE RECOVERY AND DISASSEMBLY . . . . . . . . . . . . . . . . . . 5 SPECIMEN PREPARATION ....................... 7 EXPERIMENTAL PROCEDURES ...................... 13 Neutron Dosimetry . . . . . . . . . . . . . . . . . . . . . . . 14 Thermal Monitors ....................... 15 Charpy Impact Properties ................... 16 Tensile Properties ...................... 19 Chemical Analysis of Broken Charpy Specimens ......... 21 RESULTS AND DISCUSSION ...................... 22 Neutron Dosimetry . . . . . . . . . .. ............ 22 l Analytical Methods ......................
Displacements per Atom (dpa) Analysis ............ 30 39 Thermal Monitors ....................... 41 Charpy Impact Properties ................... 45 Tensile Properties ...................... 66 Chemical Analysis of Broken Charpy Specimens ......... 75 Devel spment of Pressure-Temperature Operating Curves for Calvert Cliffs Unit No.1 ................. 78 I CONCLUSIONS REFERENCES 94 96 APPENDIX A INSTRUMENTED CHARPY EXAMINATION ................. A-1 APPENDIX B DESCRIPTION OF TRUMP ....................... B-1 APPENDIX C COMPUTER OUTPUT FOR OPERATING AND HYDROTEST PRESSURE-TEMPERATURE LIMITS AT 7.94 EFPY ,................ C-1 lI l ll i LI
I I I LIST OF TABLES l Page I TABLE 1. INVENTORY OF MECHANICAL PROPERTY SPECIMENS REMOVED FROM CHARPY AND TENSILE COMPARTMENTS FEOM CALVERT CLIFFS UNIT NO.1 CAPSULE 263 ............. 10 TABLE 2. THERMAL MONITORS . . . . . . . . . . . . . . . . . . . . 16 TABLE 3. CALIBRATION DATA FOR THE BCL HOT L/? ORATORY CHARPY IMPACT MACHINE USING AMMRC STANDARi2ED SPECIMENS . . . . 17 TABLE 4A. FAST NEUTRON 00SIMETRY RESULTS (E > 1 MeV) FOR CALVERT CLIFFS . . . . . . . . . . . . . . . . . . . . . 25 TABLE 4B. FAST NEUTRON DOSIMETRY RESULTS (E > 0.1 MeV) for CALVERT CLIFFS . . . . . . . . . . . . . . . . . . . . . 26 l TABLE 4C. TABLE 40. THERMAL NEUTRON 00SIMETRY RESULTS FOR CALVERT CLIFFS . .
SUMMARY
OF FAST NEUTRON FLUX AND FLUENCES AT VARIOUS 27 I TABLE 5. LOCATIONS ....................... CROSS SECTIONS FOR THE FLUX MONITORS (E > 1.0 MeV) IN NINE CAPSULE MESHES . . . . . . . . . . . . . . . . . 31 35 TABLE 6. CONSTANTS USED IN 00SIMETRY CALCULATIONS . . . . . . . . 36 TABLL 7. DISPLACEMENTS PER ATOM (DPA) VALUES FOR 1, 2.94, AND 32 EFPY ...................... 40 TABLE 8. CHARPY V-NT"" "1 PACT RESULTS FOR CALVERT CLIFFS IRRADIATEr .ETAL, LONGITUDINAL ORIENTATION 46 I TABLE 9. CHARPY V-Nui(H IMPACT RESULTS FOR CALVERT CLIFFS IRRADIATED WELD METAL ................ 47 TABLE 10. CHARPY V-NOTCH IMPACT RESULTS FOR CALVERT CLIFFS IRRACIATED HAZ METAL . . . . . . . . . . . . . . . . . . 48 I TABLE 11. CHARPY V-NOTCH IMPACT RESULTS FOR CALVERT CLIFFS IRRADIATED STANDARD REFERENCE MATERIAL . . . . . . . . . 49 TABLE 12.
SUMMARY
OF CHARPY IMPACT PROPERTIES FOR CALVERT CLIFFS UNIT NO. 1 ................... 62 TABLE 13. 50 FT-LB, 30 FT-LB, AND 35-MIL LATERAL EXPANSION lI TEMPERATURE SHIFTS AND DROP IN UPPER SHELF DUE TO IkRADIATION FOR CALVERT CLIFFS CAPSULE 263 . . . . . . . 62 TABLE 14A. ADJUSTED RT N VALUES FOR THE BELTLINE MATERIALS I FORCALVERTNIFFSCAPSULE263............. TABLE 14B. PREDICTED AND ACTUAL 50 FT-LB TEMPERATURE SHIFT 65
- E AND DROP IN UPPER-SHELF ENERGY FOR THE BELTLINE E MATERIALS OF CALVERT CLIFFS UNIT NO. 1 ........ 65 lI ii
!I
I I I LIST OF TABLES I (Continued) TABLE 15.
SUMMARY
OF TENSILE PROPERTIES FOR CALVERT CLIFFS UNIT N0. 1 ...................... 68 I TABLE 16. RESULTS OF X-RAY FLUORESCENCE ANALYSES OF HALF CHARPY SPECIMENS FROM CALVERT CLIFFS UNIT N0.1 CAPSULE 263. . . 76 I TABLE 17. TABLE 18. CHEMICAL ANALYSIS OF SURVEILLANCE TEST MATERIALS FOR CALVERT CLIFFS UNIT NO. 1 ............... SHIFTS IN RT NDT BASED ON RESULTS OF CHARPY TESTS . . . . 77 80 TABLE 19.
SUMMARY
OF CALCULATIONS REQUIRED FOR OPERATING CURVES . 87 TABLE 20. TEMPERATURE DIFFERENCES ................ 87 TABLE A-1. INSTRUMENTED CHARPY IMPACT DATA FOR CALVERT CLIFFS CAPSULE 263 BASE METAL ................ A-7 I TABLE A-2. !NSTRUMENTED CHARPY IMPACT DATA FOR CALVERT CLIFFS CAPSULE 263 WELD METAL ................ A-8 TABLE A-3. INSTRUMENTED CHARPY IMPACT DATA FOR CALVERT CLIFFS CAPSULE 263 HAZ METAL ................. A-9 TABLE A-4. INSTRUMENTED CHARPY IMPACT DATA FOR CALVERT CLIFFS CAPSULE 263 SRM METAL ................. A-10 LIST OF FIGURES FIGURE 1. LOCATION OF SURVEILLANCE CAPSULE ASSEMBLIES ...... 4 FIGURE 2. TYPICAL SURVEILLANCE CAPSULE ............. 5 FIGURE 3. TYPICAL TENSILE-MONITOR COMPARTMENT ASSEMBLY ..... 8 FIGURE 4. TYPICAL CHARPY IMPACT COMPARTMENT ASSEMBLY . . . . . . . 9 FIGURE 5. CHARPY V-NOTCH IMPACT SPECIMEli . . . . . . . . . . . . . 10 FIGURE 6. TENSILE SPECIMEN . . . . . . . . . . . . . . . . . . . . 12 FIGURE 7. INSTRUMENTED CHARPY MACHINE AND CONSOLE ........ 18 FIGURE 8. LOAD TRAIN USED FOR DETERMINATION OF TENSILE PROPERTIES. 20 FIGURE 9A. SURVEILLANCE CAPSULE ASSEMBLY SHOWING FLUENCE GREATER THAN 1 MEV AT THREE LOCATIONS ............. 23 FIGURE 9B. DIAGRAM OF SPECTRUM MONITCR POSITIO!!S IN HOUSING . . . 24 FIGURE 10. CALCULATED WALL FLUX (E > 1.0 MEV) iN CALVERT CLIFFS l UNIT N0. 1 . . . . . . . . . . . . . . . . . . . . . . . FIGURE 11. CALVERT CLIFFS GE0 METRY USED IN 00T RUN ........ 29 32 l fii I
I I I LIST OF FIGURES I (Continued) Page I FIGURE 12. COMPARISON OF 00T '0ECTRUM AT CAPSULE WITH FISSION SPECTRUM ........................ 34 FIGURE 13a. THERMAL MONITORS FROM COMPARTMENT N0. 4414 (TOP) .... 42 FIGURE 13b. THERMAL MONITORS FROM COMPARTMENT NO. 4441 (MIDDLE) ... 43 l FIGURE 13c. THERMAL MONITORS FROM COMPARTMENT NO. 4473 (B0TTOM) FIGURE 14A. ENERGY VS TEMPERATURE FOR CALVERT CLIFFS UNIT NO.1
... 44 50 I BASE METAL LONGITUDINAL ORIENTATION PLATE N0. D7206-3 ..
t GURE 148. LATERAL EXPANSION VS TEMPERATURE FOR CALVERT CLIFFS UNIT N0. 1 BASE METAL LONGITUDINAL ORIENTATION PLATE NO. D7206-3 ......................... 51 FIGURE 15A. ENERGY VS TEMPERATURE FOR CALVERT CLIFFS UNIT NO.1 WELD METAL PLATES 07206-2/07206-1 ............ 52 I FIGURE 15B. LATERAL EXPANSION VS TEMPERATURE FOR CALVERT CLIFFS UNIT NO. 1 WELD METAL PLATES D7206-2/D7206-1 ...... 53 FIGURE 16A. ENERGY VS TEMPERATURE FOR CALVERT CLIFFS UNIT NO. 1 HAZ METAL PLATES D7206-3/07206-1 . . . . . . . . . . . . . 54 I FIGURE 16B. LATERAL EXPANSION VS TEMPERATURE FOR CALVERT CLIFFS UNIT N0. 1 HAZ METAL PLATES D7206-3/07206-1 ....... 55 FIGURE 17A. ENERGY VS TEMPERATURE FOR CALVERT CLIFFS UNIT NO. 1 STANDARD REFERENCE MATERIAL ............... 56 FIGURE 17B LATERAL EXPANSION VS TEMPERATURE FOR CALVERT CLIFFS UNIT NO. 1 STANDARD REFERENCE MATERIAL . . . . . . . . . . 57 I FIGURE 18. CHARPY IMPACT FRACTURE SURFACES FOR CALVERT CLIFFS CAPSULE 263, BASE METAL ................. 58 FIGURE 19. CHARPY IMPACT FRACTURE Suf5 ACES FOR CALVERT CLIFFS CAPSULE 263, WELD METAL ................. 59 I FIGURE 20. CHARPY IMPACT FRACTURE SURFACES FOR CALVERT CLIFFS CAPSULE 263, HAZ METAL . . . . . . . . . . . . . . . . . . 60 FIGURE 21. CHARPY IMPACT FRACTURE SURFACES FOR CALVERT CLIFFS CAPSULE 263, SRM MATERIAL ................ 61 FIGURE 21A. COMPARISON OF 50 FT-LB TRANSITION TEMPERATURES FOR FOUR COMBUSTION ENGINEERING VESSELS ........... 67 FIGURE 22. POSTTEST PHOTOGRAPHS OF CALVERT CLIFFS TENSILE SPECIMENS FROM CAPSULE 263 . . . . . . . . . . . . . . . . 69 FIGURE 23. TYPICAL STRESS STRAIN CURVE FOR CALVERT CLIFFS UNIT NO. 1 CAPSULE 263 ................. 71 I - iv
I ! I E I LIST OF FIGURES (Continued) Page FIGURE 24. EFFECT OF IRRADIATION ON THE TENSILE PROPERTIES I FIGURE 25. 0F CALVERT CLIFFS UNIT NO. 1 BASE MATERIAL (PLATE NO. 07206-3) . . . . . . . . . . . . . . . . . . . EFFECT OF IRRADIATION ON THE TENSILE PROPERTIES 72 OF CALVERT CLIFFS UNIT NO. 1 WELD MATERIAL l (PLATENO. 07206-1/-2) ................. 73 ,g FIGURE 26. EFFECT OF IRRADIATION ON THE TENSILE PROPERTIES j OF CALVERT CLIFFS UNIT NO. 1 HAZ MATERIAL (PLATE NO. D7206-1/-3) ................. 74 15 FIGURE 27. FLUENCE AT 1/4T AND 3/4T AS A FUNCTION OF FULL 5 POWER YEARS . . . . . . . . . . . . . . . . . . . . . . . 79 FIGURE 28. NIL-DUCTILITY TEMPERATURE INCREASE AS A FUNCTION OF FAST NEUTRON FLUENCE (E > 1 MeV) ............ 82 FIGURE 29. CALVERTCLIFFS UNIT N0.1 NORMAL OPERATION HEATUP .... 90 FIGURE 30. CALVERT CLIFFS UNIT NO. 1 NORMAL OPERATION C00LDOWN . . . 91 l FIGURE 31. HEATUP CURVES AND HYDR 0 TEST .............. 92 FIGURE 32. C00LDOWN CURVES . . . . . . . . . . . . . . . . . . . . . 93 FIGURE A-1. AN IDEALIZED LOAD-TIME HISTORY FOR A CHARPY IMPACT TEST . A-2 FIGURE A-2. GRAPHICAL ANALYSIS OF CHARPY IMPACT DATA . . . . . . . . A-4 FIGURE A-3. DIAGRAM 0F INSTRUMENTATION ASSOCIATED WITH INSTRUMENTED CHARPY EXAMINATION . . . . . . . . . . . . . A-5 FIGURE A-4. INSTRUMENTED CHARPY IMPACT DATA FOR CALVERT C'_IFFS UNIT NO. 1 CAPSULE 263 BASE METAL LONGITUDINAL ORIENTATION . . . . . . . . . . . . . . . . . . . . . . A-ll FIGURE A-S. INSTRUMENTED CHARPY IMPACT DATA FOR CALVERT CLIFFS UNIT NO. 1 CAPSULE 263 WELD METAL . . . . . . . . . . . . A-15 FIGURE A-6. INSTRUMENTED CHARPY IMPACT DATA FOR CALVERT CLIFFS UNIT NO. 1 CAPSULE 263 HAZ METAL . . . . . . . . . . . . A-19 I FIGURE A-7. INSTRUMENTED CHARPY IMPACT DATA FOR CALVERT CLIFFS UNIT NO.1 CAPSULE 263 SRM MATERIAL . . . . . . . . . . . A-23
. . . A-27 I FIGURE A-8.
FIGURE A-9. THE SIX TYPES OF FRACTURE FOR NOTCHED BAR BENDING INSTRUMENTED CHARPY LOAD-TEMPERATURE CURVES FOR CALVERT CLIFFS UNIT NO. 1 CAPSULE 263 BASE LONGITUDINAL ORIENTATION . . . . . . . . . . . . . . . . . . . . . . . Ae28 FIGURE A-10. INSTRUMENTED CHARPY LOAD-TEMPERATURE CURVES FOR CALVERT CLIFFS UNIT NO. 1 CAPSULE 263 HELD METAL . . . . . . . . A-29 I FIGURE A-11. INSTRUMENTED CHARPY LOAD-TEMPERATURE CURVES FOR CALVERT CLIFFS UNIT N0. 1 CAPSULE 263 HAZ METAL . . . . . . . . A-30 v I
I E .
. I LIST OF FIGURES (Continued) , ; Pace FIGURE A-12. INSTRUMENTED CHARPY LOAD-TEMPERATURE CURVES FOR ,
CALVERT CLIFFS UNIT NO.1 CAPSULE 263 SRM MATERIAL. . . A-31 I E I I I I I I I lI I I il il I Vi _I- _ _ _ _ _ __ _ _ _ _ _ _ __.__.__
lI
- I FINAL REPORT on CALVERT CLIFFS UNIT NO. 1 NUCLEAR PLANT REACTOR PRESSURE VESSEL SURVEILLANCE PROGRAM: CAPSULE 263 to BALTIM0RE GAS AND ELECTRIC COMPANY from BATTELLE Columbus Laboratories by I J. S. Perrin, E. O. Fromm, D. R. Famelo, R. S. Denning, and R. G. Jung December 15, 1980
SUMMARY
I Capsule 263 was removed from the Calvert Cliffs Unit No.1 Nuclear Power Plant after 2.94 equivalent full power years of reactor operation. The capsule was sent to the Battelle Columbus Hot Laboratory for examination and evaluation. The irradiation temperature did not exceed 580 F as indicated by the examination of the 12 themal monitors. The maximum neutron fluence occurred at the location of the weld metal specimens in the bottom of the 18 n/cm2 (E > 1 MeV), using capsule assembly. It was detemined to be 6.2 x 10 I the average of the copper, iron, and nickel neutron dosimeters. At the vessel I9 wall the maximum exposure was detemined to be 4.7 x 10 n/cm at 32 effec-I tive full power years (EFPY). The neutron radiation value associated with the irradiation was calculated to be 6.9 x 10-2 displacements per atom (dpa) for 32 EFPY. The caps le fluence leads the inner wall of the pressure vessel by a factor of 1.43. I Chemistry of broken Charpy specimens was perfomed using the method of x-ray fluorescence. Results for the nine elements showed the compositions to be close to those reported in the original chemical analysis of the sur-veillance materials. I
I I I The radiation-induced changes in the mechanical properties of the pressure vessel material we e determined. Evaluation of the tensile property specimens included the yield, ultimate, and fracture strengths as well as I elongation and reduction in area. Charpy impact specimens were used to deter-mine changes in the impact behavior, including the shifts in the transition I temperature region and the drops in the upper shelf energy level. The weld heat affected zone material showed the greatest shift in the 30 and 50 I ft-lb transition temperature as well as for the 35 mil lateral expansion temperature, and is the limiting material. The adjusted RT ilDT for this mate-I rial is 106 F. Heatup and cooldown operational limit curves for the reactor vessel were developed based on this material for the period of 2.94 to 7.94 EFPY. I I I I I I I I I I I I I
I I I INTRODUCTION I Irradiation of materials such as the pressure vessel steels used in I reactors causes changes in the mechanical properties, including tensile, impact, and fracture toughness.(1-6)* Tensile properties generally show a decrease of both uniform elongation and reduction in area accompanied by an increase in yield strength and ultimate tensile strength with increasing neutron exposure. The impact properties as determined by the Charpy V-notch impact test generally show a substantial increase in the ductile to brittle transition temperature and a drop in the upper shelf energy. Commercial nuclear power reactors are put into operation with reactor pressure vessel surveillance programs. The purpose of the surveillance program associated with a reactor is to monitor the changes in mechanical properties as a function of neutron exposure. The surveillance program includes a detemination of both the preirradiation baseline mechanical properties and periodic detemina-tions of the irradiated mechanical properties. The materials included in a sur-veillance program are base metal, weld metal, and heat-affected-zone metal from the actual components used in fabricating the vessel. In addition, speci-mens fabricated from ASTM Standard Reference Material are sometimes included for comparison. The irradiated mechanical properties are determined periodically by l testing specimens from surveillance capsules. Six surveillance capsules each containing mechanical property specimens (Charpy and tensile), dosimeter moni-tors and themal raonitors were inserted in the reactor pressure vessel as shown in Figure 1 prior to initial plant startup. Capsules are periodically removed, and sent to a hot laboratory for disassembly and specimen evaluation. I
- References at end of text.
** To be consistent with Reference 7, the tam Standard Reference Material (SRM) will be used throughout this report rather than Correlation Monitor Material.
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I 5 I Calvert Cliffs has a surveillance program which is described in a report issued b/ Combustion Engineering.(7) The program is based on ASTM E185-66 "urveillance Tests on Structural Materials in Nuclear Reactors"(0) , and is conducted using numerous other ASTM standards.I9) At the time of initial operation of the reactor, the pressure-temperature operating curves were specified. During the life of the reactor, the curves are to be revised to account for the changes in the Charpy impact behavior of the vessel materials. A previous report covers the preirradiation base-line tensile and Charpy impact properties of four materials from Calvert Cliffs Unit No,1 00) , These materials include base metal longitudinal orientation, weld metal, heat l affected zone metal, and Standard Reference Material (SRM). The present report describes the results obtained from examination of wall Capsule 263 which was removed from the reactor during May,1979. CAPSULE RECOVERY AND DISASSEMBLY Battelle shipping cask BCL-4 was sent to the reactor site to pick up the surveillance capsule which was stored in the spent fuel storage pool. Reactor personnel loaded the capsule into the shipping cask and the cask was then shipped from the reactor site to the BCL Hot Laboratory for postirradia-tion examination. Upon arrival at BCL, the capsule was removed from the cask and I transferred to a hot cell for visual observation, photography, and disassem-bly. Visual examination showed no unusual features or damage. Figure 2 shows a sketch of a typical surveillance capsule from I Calvert Cliffs Unit No.1. The capsule compartments were cut apart using a flexible abrasive wheel attached to a Mototool. The capsule contained four I Charpy compartments and three tensile-monitor compartments. The identifica-tion numbers of these compartments are as follows, with the first being located I at the top end of the capsule and the last being located at the bottom end of the capsule assembly. I 1 I I .
- I I 6 I
,I TENSILE-MONITOR CHARPY IMPACT COMPARTMENTS 1 l .I N TENSILE-MONITOR COMPARTMENT l 1I , i CHARPY IMPACT COMPARTMENTS I I 9% I TENSILE-MONITOR COMPARTMENT l I FIGURE 2. TYPICAL SURVEILLANCE CAPSULE I - I I '
I l 4414 Tensile-monitor compartment 4424 Charpy compartment 4436 Charpy compartment l 4441 4451 Tensile-monitor compartment Charpy compartment 4463 Charpy compartment 4473 Tensile-monitor compartment. Each tensile-monitor compartment contained three tensile specimens, a set of 4 cadmium shielded flux monitors, a set of 5 unshielded flux monitors, and a set of 4 temperature monitors. The arrangement of the flux monitors, thermal monitors, and tensile specimens within a given tensile-monitor compartment is shown in Figure 3. A typical Charpy compartment, each of which contained 12 Charpy specimens, is shown in Figure 4. An inventory of the mechanical property specimens from the capsule is listed in 4He 1. l SPECIMEN PREPARATION The Calvert Cliffs Unit No.1 reactor vessel is fabricated from steel plates according to ASME Specification SA533 6.ade B with Class 1 mechanical properties as described in Reference 7. The mechanical test specimens for the surveillance capsule were prepared from intermediate shell course plates D7206-1, D7206-2, and D7206-3. The base metal surveil-lance test specimens were fabricated from intemediate shell plate D7206-3. The weld metal surveillance test specimens were fabricated from the simulated girth weld between intemediate shell plates D7206-1 and D7206-2. The HAZ metal surveillance test specimens were fabricated from the 07206-3 side of shell plate D7206-1 and D7206-3. The chemistry of the material used for the surveillance specimens is reported in the Chemistry Section of this report. The procedure for preparation of the test specimens is described in Reference 7. Figures 5 and 6 show the design of the two types of mechanical property specimens that were irradiated in Capsule 263. The Charpy impact specimen is shown in Figure 5 and is the standard specimen reconsnended in ASTM E23-72 . The tensile specimen design shown in l Figure 6 has a nominal 0.250-in. gage diameter and a nominal 1.00-in. gage length. I I
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I I 10 I I l TABLE 1. INVENTORY OF MECHANICAL PROPERTY SPECIMENS REMOVED FROM CHARPY AND TENSILE COMPARTMENTS FROM CALVERT CLIFFS UNIT NO. 1 CAPSULE 263 I Compartment No. Material Specimen Identification Charpy Compartments 4424 !iAZ 44A 445 43U 43P 43Y 43T 447 44J 446 44K 440 44C I 4436 Standard Reference Material 646 64E 646 64A 647 648 64J 645 644 64D 643 642 I 4451 Base (Longitudinal) 142 143 147 144 145 14C 146 140 14J 148 14A 14E I 4463 Weld 34K 34E 34M 340 34J 34L Tensile Compartments 4414 HAZ 4KA 4K6 4K7 ,I j 4441 Base (Longitudinal) lJT lJA IJP 4473 Weld 3K5 3K3 3K7
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I l 13 The longitudinal base metal specimens are defined as those with their major axes parallel to the major rolling direction of the source 1 test materials. Longitudinal weld metal specimens are defined as those I with their major axes parallel to the centerline of the as-deposited weld. Transverse weld and HAZ metal are defined as those with their major axes I perpendicular to the centerline of the deposited weld. The standard re-ference material specimens were machined to have longitudinal orientation. I EXPERIMENTAL PROCEDURES This section describes the experimental procedures used in the determination of the neutron exposure, examination of the thermal monitors, l the detennination of the Charpy impact and tensile properties, and chemical analysis. All testing was conducted at Battelle's Columbus Labora-l tories according to applicable ASTri procedures. The data for the program are recorded in the BCL Laboratory Record Books 35730 and 36839. I I I I i lI I l I I l I !
- I l
I I 14 Neutron Dosimetry Description of Flux Monitors The capsule contained 27 flux monitors. Nine of these are located in ea:h of three tensile-monitor compartments. A typical tensile-monitor compartment is shown in Figure 3; each compartment contains two flux-monitor housings. One housing contains aluminum-cobalt (Al-Co), uranium (U), titanium (Ti), iron (Fe), and sulfur (S) flux monitors encapsulated in l stainless steel sheaths (except for 5 which is encapsulated in quartz). The other housing contains Al-Co, U, Ni, and Cu monitors within cadmium shielding to pr'a ent competing thermal reactions. The six materials V, Ti, Fe, S', Ni and Cu are used in determining the fast fluence with neutron energies greater than 0.1 and 1 MeV. Thermal flux is determined from the Al-Co monitors. Removal of Monitor Wires The three individual flux monitor compartments were opened in a hot cell. Twenty-seven sheathed flux monitors wEre recovered, verified and placed in marked vials. The three sulfur monitors contained in quartz were discarded l due to the short half-life,14.3 di of the product. The remaining twenty-four sheathed flux monitors were removed from the cell. The individual sheaths were decontaminated to <5000 dpm s-Y smearable, and then transferred to the radio chemistry laboratory. Each sheath was opened with a mini-tubing cutter and either the bare or admium-covered monitor was recovered and cleaned to
<200 dpm S-Y smearable. They were weighed to 0.1 mg and mounted for gamma counting.
The uranium monitors were recovered in powder form of 30 to 40 mg l quantities and carefully transferred into tared vials. They were weighed to l t 0.1 mg and gama scanned for presence of impurities such as Cd-109 and Ag-110m. The powder was then dissolved in nitric acid and diluted to 50 ml. , Suitable quantities were pipeted for gamma analysis of the desired fission l l product and for uranium isotopic analysis by mass spectroscopy. lI lI 'I
I I I 15 A 50 cc intrinsic germanium detector and Ortec Model 7010 I multichannel analyzer (4096 channels) were used for gamma analysis. The system is capable of 2.0 kev resolution at the 1332 kev gamma peak of Co-60. I ASTM procedures were used for the appropriate monitor. The references are as follows: I ASTM E261-77. " Determining Neutron Flux, F Radioactivation Techniques." pce and Spectra by i W E ASTM E262-77. " Determining Techniques."grmal Neutron Flux by Radioactivation ASTM E263-77. "Determin of Iron." ) Fast Neutron Flux by Radioactivation ASTM E264-77. "Determinin F of Nickel." 15fst Neutron Flux by Radioactivation ASTM E523-76. " Measuring Fast Ne t n Flux Density cy Ladioacti-vation of Coppar." l ASTM E526-76. " Measuring Fas N of Titanium."l{7)eutron Flux by Radioactivation ASTM E704-79. " Determining Fast Neutron F
) Density by Radio-activation of Uranium-238."
Results of the counting a ad analysis are presented under Neutron Dosimetry l in the Results and Discussion section of this report. l Thermal Monitors I The capsule contained four kinds of low-melting-point alloy wires for determination of the maximum temperature attained by the test specimens during the irradiation period. A typical thermal monitor consisted of a helix of wire of a particular alloy composition located below a stainless steel weight inside a quact tube. Identification of a specific type of thermal monitor was by measurement of the overall length of the quartz tubing. The identification of each of the four alloys in a given thermal monitor compartment is given in Table 2. I l I
I I 16 I I TABLE 2. THERMAL MONITORS Length of Quartz Composition of the Melting Point, Capsule, in. Alloy, Percent F 1 80.0 Au, 20 Sn 536 l-1/4 90.0 Pb, 5.0 Sn, 5.0 Ag 558 l 1-1/2 97.5 Pb, 2.5 Ag 580 1-3/4 97.5 Pb, 0.75 Sn, 1.75 Ag 590 I A set of four thermal monitors were located in each of the three tensile-monitor compartments. The location of the temperature monitors within a given compartment is shown in Figure 3. During capsule disassembly, the four thermal monitors were re-covered from each of the three compartments and examined for evidence of l melting using a stereomicroscope at a magnification of about 4X. I Charpy Impact Properties The Charpy impact tests were conducted using a 240 ft-lb Satec-Baldwin I MODEL SI-lC impact machine in accordance with ASTM E23-72UI) . The 240 ft-lb range was used for all tests. The velocity of the hammer at impact was a 16.95 ft/sec. The calibration of the machine was verified as specified in ASTM E23-72 and proof tested using standardized Charpy impact specimens I purchased from the U.S. Army Materials and Mechanics Research Center (AMMRC). The results of the most recent proof tests run on February 13, 1980, are listed I in Table 3. I I I I
I I 17 I TABLE 3. CALIBRATION DATA FOR THE BCL HOT LABORATORY CHARPY IMPACT MACHINE USING AMMRC STANDARDIZED SPECIMENS I l Average AMMRC Standard BCL Energy. Energy (a) , Variation l Group Ft-Lb Ft-Lb Actual Allowed Low Energy 14.4 14.5 -0.1 f t-lb tl.0 ft-lb High Energy 72.3 72.5 -0.3 percent t5.0 percent I (a) Established by U.S. Army Materials and Mechanics Research Center. I The instrumented Charpy impact machine is shown in Figure 7. The signal conditioner associated with instrumented Charpy testing is mounted on l top of tne instrument console. The digital oscilloscope, located in the lower g lef thand corner of the console, is used to digitize and record load-time data generated during impact tests (I9) The x-y recorder located to the right of the console is used to produce x-y plots of the load-time curves from the oscilloscope trace. Various attenuations are available for expand-ing the oscilloscope curves (in the x-y directions). A digital temperature readout, used to monitor the temperature of the liquid baths, is located to the right of the signal conditioner on top of the console. A mini-computer, which is used to obtain auxiliary Charpy impact energy independent of the dial energy, is located in the top of the console panel. ASTM procedures for specimen temperature control were utilized. The j low-temperature bath consisted of agitated methyl alcohol cooled with additions of liquid nitrogen. The container was a Dewar flask which contained a grid to keep the specimens at least 1 inch from the bottom. The height of the bath was enough to keep a minimum of 1 inch of licuid over the specimens. The Charpy specimens were held at temperature for a minimum of at least the ASTM recomended time. I I
'I
- I I l
~
1 I 'i:; I l I
/
i '
- v. / . ;,. < :
I
~
ag.- ll
\,n.__ .' - -
g \;= . a.. . ,
- . 2 =. .g .4 tre m _ 3-
- M_ '
,I
.;f6' % *? - . .
I y/
%Fy2 ,
;pr ?
S I I I I FIGl'RE 7. INSTRUMENTED CllARPY MACllINE AND CONSOLE The instrument console is in the center I and the x-y plotter is on the right side of the photograph. I I -___________--_1
1 I 1 19 Tests above room temperature were conducted in a similar manner except 8 that a metal container with a liquid bath was used. The bath used oil for temper-atures above 80 F. I The specimens were manually transferred from each temperature bath to the anvil of the impact machine by means of tongs that had also been brought to tempera-I ture in the bath. The specimens were removed from the bath and impacted in less than 5 sec. The energy required to break the specimens was recorded and plotted I as a function of test temoerature as the testing proceeded. Lateral expansion was determined from measurements made with a lateral I expansion gage. Fracture appearance was obtained from 2X photographs of the fracture surfaces by measuring the shear area using a planimeter and comparing this with the total fracture area (20) , Tensile Properties Tne tensile tests were conducted on a screw-driven Instron testing j machine having a 20,000-lb capability. Crosshead speeds of 0.005 and 0.05 inch per minute were used. The defomation of the specimen was measured to a point just beyond the maximum load by using a strain gage extensometer. Deformation beyond the maximum load was measured using the crosshead speed (0.05 in./ min) and the elapsed time. The strain gage unit senses the differential movement of two extensometer extension arms attached to the specimen gace length 1-inch apart. The extension ams are required for thermal protection of the strain gage unit during elevated temperature tests. Figure 8 shows the extensometer extension ams and strain gage assembly used for tensile testing. The strain gage unit is shown at the bottom left of the figure next to the region of the extensometer arms where the unit is attached during testing. The extensometer was calibrated before testing using an Instron high-magnification drum-type extensometer calibrator. The irradiated tensile specimens were tested at room temperature, 250 F and 550 F. Elevated temperature tensile tests were conducted using a hot air-furnace. The specimens were held at the test temperature for 20 minutes before testing as required by ASTM. Specimen temperature was monitored using two Chromel-Alumel themocouples attached directly to the specimen within the gage section o.f the specimen. Temperature was controlled within +5 F throughout the 20 minute soak period as well as for the actual tensile ' test. I
I li , l
\\ l ;
l PULL R0D ' f) S l KNIFE EDGE l E SPECIMEN (HIDDEN) l KNIFE EDGE I PULL ROD- , l EXTENSOMETER EXTENSION ARM , CLIP GAGE f / lI l 8
#D FIGURE 8. LOAD TRAIN USED FOR DETERMINATION OF TENSILE PROPERTIES
.E Specimen is located under extensometer knife E edgc8 in center of photograph. Clip-on strain gage attached to extensometer arms is shown in lower region of photograph. lI lI.________--.-- . - _ _ - . _ _ - .
I I 21 I Load-extension data were recorded on the testing machine strip I chart. The yield strength, ultimate tensile strength, fracture strength, uniform elongation, and total elongation were determined from these charts. I The reduction in area was determined from specimen measurements made using a blade micrometer. The total elongation was determined from the increase in distance between two punch marks which were installed 1-inch apart on the gage length prior to testing. Chemical Analysis of Broken Charpy Specimens Chemical analysis of ten broken Charpy specimens for copper (Cu), phosphorous (P), sulfur (S), vanadium (V), nickel (Ni), molybdenum (Mo), manganese (Mn), chromium (Cr) and Silicon (Si) was performed using the method of x-ray fluoresence (XRF). Each sample, which consisted of a separate half of a broken base or weld metal Charpy specimen, was polished through 600 grit to provide a satisfactory surface for analysis. Both tantalum and aluminum masks were used to accomodate the sample. The masked-down sample as well as the NBS standard is bombarded with primary x-rays to produce measurable characteristic x-rays of the desired elements. The characteristic or secondary x-rays which result from the inner orbital electron transitions are produced in proportion to the amount of the element in the sample. Quantification is achieved by comparing the accumulated intensities from the samples to those l from certified NBS standards. The procedure used involved counting on the major lines and at off-line background positions. Counts were accumulated up to 200 seconds at least twice for each sample. Electronic pulse height analysis (PHA) elimina-tion of excessive background due to the radioactivity of the samples was l incorporated for sulfur, vanadium, silicon and phosphorous to provide for greater sensitivity in the net intensity ef elements at lower concentrations. I 'I I . I I
l' t 'I RESULTS AND DISCUSSION Neutron Dosimetry Capsule 263 was in the reactor for 1073.32 equivalent full power days or 2.94 equivalent full power years (based on a reactor full power of 2700 MWt ). The capsule was located at a core position of 263 and was positioned radh11y approximately 0.6 inches from the inner vessel wall. The capsule contained three flux monitor compartments which, dis-cussed earlier, were located near top, near middle and near bottom of the capsule as shown in Figure 9A. Each compartment contained a set of bare monitors and a set of cadmium-covered monitors. Figure 9B shows a horizontal cross-sectional diagram of the capsule at the bare monitor housing and at the cadmium-covered monitor housing. The capsule was modeled as a 1.54 inch by 2.21 inch rectangular tube with a 0.138 inch wall which includes the capsule holder. The positions of all the monitors (iron, nickel, copper, titanium, uranium and cobalt-aluminum alloy) are shown in Figure 98. The monitors were counted for activation product gamma ray activity, and the DOT code and the DECAY code were used to determine the fluence at each monitor. The thermal fluence results and the fast fluence results for energy greater than 1 MeV and 0.1 MeV, are shown in Tables 4A, 48, and 4C. Good agreement was obtained among the iron, nickel, and copper dosimeters. The titanium results were 20 to 30 percent higher, and were not considered valid due to the condition of the postirradiated wires. They were very brittle and a copper color which was assumed to be titanium nitride. The uranium (Ce-144) results were also about 20 percent higner, but were disregarded due to the poor condition of the postirradiated foils. They were recovered as a finely divided black powder, and in the case of the shielded set, they had reacted with the low melting cadmium (MP = 608 F) to provide poor specimens. It is believed that the individual spin-closed stain-less steel monitor capsules allowed some air to oxidize the uranium and nitride the titanium metal. The capsules were not tightly sealed and a small hole could be observed in most containers. , i l I l
a_A,- a-s- -n m--- m a m,- a1- e- __--_aw _ -- - 6a -.-Mama---- - - - - . - - - - - ~ = - _m -a !I . I 23 !.I i l TENSILE-MONITOR 7 6.1 x 1018n/cm 2 !g lI : l CHARPY l'MPACT COMPARTMENTS I - !8 I T _ ._ _ COMPARTMENT " s) i
% 5 .8 x 1018 ,f,,2
!I I q L_ _CT __T. I J I q s TENSILE-MONITOR 6.2 x 1018n/cm 2
~
COMPARTMENT I FIGURE 9A. SURVEILLANCE CAPSULE ASSEMBLY I SHOWING FLUENCE GREATER THAN 1 MEV AT THREE LOCATIIONS. I
I I u I - I BARE MONITORS f, g g s e u U Co m -
-- g I 1.
2.81
- 3. 63 I 4.45 I .- _
g su I I CAOMIUM COVEREO ' l MONITORS CU NI U CD-AL
~ 1.34 -
2.32 I 3.31
, 4. 2.
'I I I FIGURE 98. DIAGRAM OF SPECTRUM MONITOR POSITIONS IN HOUSING. (ALL I DIMENSIONS IN CENTIMETERS) I - -- _ _ _ _ . _ _ _
M M M M M M M M M M M M M M M mM M M M m' W TABLE 4A. FAST NEUTRON DOSIMETRY RESULTS (E > 1 MeV) FOR CALVERT CLIFFS i Fe + Mn54 N1 -. CoS8 Cu + Co60 T1 + Sc46 U238 + Ce144(b) Activity,a) Fluen e. Activity. Flue e. Activity. Capsule Fluence. Activity. dps/mg n/cm dps/mg n/ dps/mg dps/mg Fluenge' tivit n/cm2 n/cm hpsfag CI.Fluenci-
) n/cm T p com- 3 18 4 3.6611.0Zx10 5.92x10 6.0211.0Zx10 5.99x10 18 2 1.9611.8%x10 6.31x10 18 3 1.47 1.6%x10 7.95x10 IO 2 7.23x10 18 partment 3.2511.0%x10 4414 Avg of Fe N1 Cu Fluences-- IO 6.113.4%x10 Middle 3 18 4 18 2 18 3.4511.0%x10 5.58x10 5.4611.0Zx10 5.43x10 1.9611.8%x10 6.29x10 3
7.00x10 18 3 18 compart- 1.2911.6%x10 3.1711.0Zx10 7.04x10 ment 4441
~
Avg of Fe, Nl. Cu Fluences-- 18 sn 5.818.0!x10 Bottom 3 18 4 18 2 18 3.5711.0!x10 5.77x10 6.0911.0%x10 6.06x10 3 18 2 18 compart- 2.1311.6%x10 6.48x10 1.3611.8%x10 7.35x10 3.5611.0%x10 7.89x10 ment ! 4473 Avg of Fe, NI. Cu Fluences-- l0 6.218.9%x10 (a) At shutdown. EOC 3. 2200 hours. 4/20/79. (b) Based on a fast fission yield of 4.54 percent. (c) Includes 0.9 correction factor for 300 ppa U235 and 100 ppe Pu239 impurities. (d) Per milligram of uranium basis fran mass spectroscopic analysis. (e) Errors quoted are 2a values from counting statistics only. Accuracles are 15 percent for Fe, N1 Cu. T1; 110 percent for U238. (f) Errors are lo values.
i I 26 l I l lI ! I TABLE 48. FAST NEUTRON 00SIMETRY RESULTS (E > 0.1 MeV) FOR CALVERT CLIFFS NO.1 I Location Fast Fluence (n/cm ), E > 0.1 MeV (a) (b) in Capsule Fe Ni Cu Ti U2384e144 l9 l9 l Top compart- 1.13 x 10 I9 1.14 x 10 I9 1.20 x 10 1.52 x 10 I9 1.38 x 10 ment 4414 , , , Fe, Ni, Cu (avg) = 1.16 1 3.3% x 10 l9 lI Middle com- 1.06 x 10 I9 1.04 x 10 I9 1.19 x 10 I9 1.34 x 10 I9 1.34 x 10 I9 I partment 4441 i Fe, Ni, cu (avg) = 1.10 1 7.4% x 10l9 I9 I9 l9 1.50 x 10 I9 Bottom com- 1.10 x 10 I9 1.16 x 10 1.30 x 10 1.41 x 10 partment ; ' i I 4473 Fe, Ni, Cu (avg) = 1.1918.6% x 10 I9(c) 'I (a) Includes 0.9 correction factor for 300 ppm U235 and 100 ppm Pu239 impurities. (b) Based on a fast fission yield of 4.54 percent. l (c) Errors are lo values. I lI I . 'I I
'I I 27 I I TABLE 4C. THER".AL NEUTRON 00SIMETRY RESULTS FOR CALVERT CLIFFS UNIT NO. 1 Thermal (c) location 2 (a) Fluence, Thermal Fluence (n/cm ) 2 Ca ule bare Cd covered R(b) n/cm I 18 18 I Top Mid 9.35 x 10 1.01 x 10 I9 18 1.20 x 10 1.21 x 10 18 18 7.79 8.32 8.1 x 10 8.9 x 19 18 18 Bottom 7.13 x 10 1.19 x 10 5.99 5.9 x 10 I (a) Based on a cobalt content of 0.17 percent for the Al-Co monitor wires. (b) R = Cadmium Ratio = Cobare/CoCd covered - l (c) True Thermal Fluence = Cobare * * 'I , I I I I I I I - I lI . _ .. . . _.
I 28 Frequently, iron monitors only have been used to calculate the fluence exposure. However, due to improved techniques for cross section measurement and correction for the reaction threshold, as discussed in the next section on analytical methods, it was decided that the average of the three monitors Fe, fli, and Cu would result in the best experimentally de-termined value. flickel was included, although it has a relatively short half-life, since (1) it is chemically stable, (2) it has a low reaction threshold energy of about 1 MeV, and (3) growth and decay corrections through-out the three cycle operation are made with the DECAY computer code (See Ana-l lytical Methods). Consecuently, the average of the Fe, fli and Cu fluence results was used to calculate the fluence seen by surveillance Capsule 263. These averages and the product activity at shutdown are shown for each compartment in Tables 4A and 48. I8 2 The results for fluence for E > 1 MeV are 6.07 x 10 n/cm for 18 top compartment, 5.77 x 1018n/cm2 for the middle compartment and 6.22 x 10 for the bottom compartment. These results are also shown in Figure 9A. The I9 I9 corresponding fluences for E > 0.1 MeV are 1.16 x 10 for the top,1.10 x 10 I9 for the middle and 1.19 x 10 for the bottom compartments. Thus, these results indicate that the fluence near the core center line is smaller than that either above or below the center line. Conversely, the thermal fluence (Table 4C) is highest at the center compartment. 10 , l Using the highest flux (E > 1 MeV) in the capsule (6.71 x 10 n/cm /sec at full power in the bottom compartment), the fluxes at the inside of the wall, at 1/4T and at 3/4T were calculated. The highest flux was used in order to represent a highest exposure situation. These are shown in Figure 10 as a function of angular position. As can be seen, the presence of the capsule causes a fairly significant depression of the flux near it. The lead factor, i.e., the ratio of the flux at the capsule to the largest flux received by the wall at any zximuthal wall location, is approximately
- 6.71 x 1010/4.7 x 1010 = 1.43 (where a compensation for flux depression at the wall has been made). The predicted maximum wall fluence after 32 EFPY
.I I 3
I I 29 l 10 11 l CAPSULE FLUX =6.71X1B I :5
~
PRESSURE VESSEL INNER RADIUS l O I s ~ E
- V
$ 1/4 THICKNESS I S sig lE -
I e g T 0 z N ~ 3/4 THICKNESS 1 l . ,l CAPSULE 263 g , I i i . i i i i 10 255 285 275 225 235 245 l AZIMUTHAL ANGLE (DEG) I FIGURE 10. CALCULATED WALL FLUX (E>1. 0 IN CALVERT CLIFFS UNIT I MEV) NO. 1. I I. - - _-__ ______--- - _ _ .
30 is then 4.74 x 10 I9 n/cm . This compares reasonably well with the Technical 2 Specification value of 3.44 x 10 I9 n/cm2 . The fluence at the 1/4 T position is 0.574 that at the inner wall and the fluence at the 3/4 T position is 0.132 that at the inner wall. These values are summarized in Table 4D. Analytical Methods The detennination of the neutron flux at the capsule, and subse-I quently in the pressure vessel wall, requires the completion of three proce-dures. First, the disintegration rate of the product isotope per unit mass of g 5 the flux monitor must be determined. This has been discussed earlier under experimental procedures. Second, in order to find a spectrum-averaged reaction cross section at the capsule location, the neutron energy spectrum must be cal-I culated for that identical location. Third, the neutron flux at the capsule must be found by calculations involving the ccunting rate data, the spectrum l averaged cross sections, and the operating history of the reactor. The energy and spatial distribution of neutron flux in the reactor were calculated using the DOT 3.5 computer program . DOT solves the Boltzman transport equation in two-dimensional geometry using the method of l discrete ordinates. Balance equations are solved for the density of particles moving along discrete directions in each cell of a two-dimensional spatial l mesh. Anistotropic scattering is treated using a Legendre expansion of arbitrary order. I The two dimensional geometry that was used to model the reactor is shown in Figure 11. As seen there are 19 circumferential meshes and 52 radial I meshes. Capsule 263 includes circumferential meshes 13,14, and 15 and radial meshes 36, 37, and 38. Third order scattering was used (P 3) and 48 angular directions of neutron travel (24 positive and 24 negative) were used (S8 quad-rature). Neutron energies were divided into 22 groups with energies from 14.9 MeV to 0.01 eV. The 22 group structure is that of the RSIC Data Library DLC/ CASK (22) , and neutron absorption, scattering, and fission cross sections used are those supplied by this library. The core shroud and the core support barrel are type 304 stainless j steel. The capsule is also modeled as a solid piece of 304 stainless steel. The reactor pressure vessel wall is A5338 steel. The reactor core was mocked I .I
I ~ I 31 I I 'I TABLE 40.
SUMMARY
OF FAST NEUTRON FLUX AND FLUENCES AT VARIOUS LOCATIONS I Fast Fluence (E > 1.0 MeV)(a) Predicted From Maximum (a) After 2.94 After 32 Technical I Location Flux, n/cm2/sec EFPY EFPY Specifications I W 263 Surveillance Capsule 6.7 x 10 10 6.2 x 10 18 6.8 x 10 19 - Pressure Vessel Wall Inner Diameter 4.7 x 10 10 4.4 x 10 18 4.7 x 10 19 3.4 x 10 19 1/4 Thickness of Vessel Wall 2.6 x 10 10 2.4 x 10 18 2.6 x 10 19 - 3/4 Thickness of g j7 jg Vessel Wall 6.1 x 10 5.6 x 10 6.1 x 10 - I (a) Note from test that the largest fast flux (E>l MeV) at the bottom of the capsule was used for all estimates. The actual measured center flux was 7.2% lower than the bottom value. See Figure 6A. 1 I I 1 'I 'I .
I I 15,14,13 1"I " I' 22y 5 ,% f ,n g I s
#3Sgg 4 l ~ -
MM l HO 2
/ ,
I ,,;; _L m_; * ** %,, 'op
. 160 N /4 5 155.83 \"""""""" M frp !- Zid'hy k /[' /'"/
u 135.05 N \ nuwwN P I I l,,:=; IIN,Nl
- 5, S 4 '
'*+
100 --
\/ b,e Q
9330
.0 _.
[ E E V WE N E I 0 . I 41.53 I ! ! ! ! ! ! 20 ' I 0 20 40 80 80 100 DISTANCE FROM CORE CENTER, em 120 140 160 180 FIGURE 11. CALVERT CLIFFS GEOMETRY USED IN DOT RUN. I
I I 33 up as homogenized fuel and water having the densities found in the operating reactor. The water in the core region has a density consistent with the average coolant temperature in the core (570 F) at the operating pressure of 2250 psia. The water in the downcomer region outside the core barrel had a density consistent with the inlet coolant temperature (543 F) and operating pressure of 2250 psia. All the water carried boron in solution at the concen-I tration specified for full power operation, i.e., 725 grams of boron per 106 grams of water. Finally, the fuel was a source of neutrons having a U-235 fission energy spectrum. The relative power in the assemblies nearest the I capsule, during the interval the capsule was in the reactor, is shown in Figure 11 . The neutron spectrum at the capsule center, as calculated by D0T, is shown in Figure 12. Also shown for comparison is the fission spectrum. I Both spectra have been normalized to contain one neutron above 1.0 MeV. As can be seen, the capsule spectrum is very much harder than the fission spec-I trum. This is caused by travel through water. The D0T calculated values of
" spectrum-averaged" cross-section,R o , differ from the fission spectrum-I averaged cross sections by as much as a factor of 2.
Based upon the fluxes calculated by D0T at r mesh 37 and e mesh I 13, 14, and 15 (the three radial centered meshes used to represent the capsule and the region in which the flux monitors were placed), effective I cross-sections oR (E>0.1 MeV) and og (E>1.0 MeV) defined as I o R(E>Ec)= I o (E)e(E)dE
=
I Ec *( h were calculated for iron, nickel, copper, titanium, and uranium in each of the three e meshes. The results are shown in Table 5 for oR (E > 1.0 MeV) which is of most interest. These values differ from center to edge of the l capsule because the fast spectrum is being depressed by the capsule presence as was shown earlier and because the neutron spectrum is being modified by the stainless steel of the capsule. Using the results of Table 5 and the geometry shown in Figure 98, the cross-section appropriate to each of the monitors can be interpolated. These values and other nuclear constants needed in the third step of the flux-finding procedure are given in Table 6. I I
l 1 1 lI i 34 lI i m
;~*..i.i i.i.,.,.;
I j FISSION SPECTRUM -
- - - - - CAPSULE SPECIRUM l
= --- -
( =
~
i [ j j .
,g g .
5 w . _ _ _ _ . , . (N l 4 I s 's 5
=
E - l 3 g . g .
- I F-y wm 41
----i l
!= w a- . . lg 3 : I o : : : E . y I w . ____ I , i m :~ I IS I . 8 I e 1 : I e i e I e I i l e B 2 4 6 8 10 12 14 NEUTRON ENERGY (MEV) g I FIGURE 12. COMPARISON OF OOT SPECTRUM l AT CAPSULE WITH FISSION SPECTRUM. I I
I I 35 I TABLE 5. CROSS-SECTIONS FOR THE FLUX MONITORS (E>l.0 MeV) IN NINE CAPSULE MESHES I Core 4
.00148 .00142 .00148 CopperCross-Sections (barns)
Corep
.170 .165 .170 I
Nickel Cross-Sections (barns) Core 9 g o
.134 .129 -
.134 Iron Cross-Sections (barns)
Coref
.0225 .0216 .0225 l Titanium Cross-Sections (barns)
Core A l .423 .418 .423 Uranium Cross-Sections (barns) I L - . .. _
I l 36 lg I I I TA8LE 6. CONSTANTS USED IN D0SIMETRY CALCULATIONS I Cross-Sections Isotopic Threshold (Barns) l3 Target, Abundance, Energy, Product E>1.0 MeV E Reaction % % (MeV) Half-Life E>0.1 MeV Fe 54(n,p)Mn54 99.865Fe 5.82 1.5 314d .131 i
.0688 Cu 63(n,a)Co 60 99.999Cu 69.17 5.0 5.26y .00147
.00078 I Ni S8(n,p)Co S8 99.951Ni 67.77 1.0 71.3d .166
.087 I Ti46(n,p)Sc46 99.793T1 7.93 2.5 83.8d .0216
.0113 U238(n,f)Ce144 100.0(a)U 99.97(b) 0.8 284.1d .420 E .221 l5 1
' (a) The target was considered 100.0% uranium since the oxide powder was dissolved and analyzed as mg U/mi solution. (b) The uranium monitor was analyzed to contain 0.03% U-235 (300 ppm). I l I I I . I. . . -- . . . .-.
37 In the third step the full power flux at the capsule location is determined from the radioactivity induced in the monitor foils, the spectrum-averaged cross-sections calculated for the monitor elements, and the power history of the reactor during capsule exposure. The fluence at the capsule is then calculated from the integrated power output of thr; reactor I during the exposure interval. The activity A induced into an element irradiated for a time I t gin a constant. neutron flux is given by
= -At A = N [I o (E)o(E)dE] (1-e I) where a(E) = the differential cross section for the activation reaction l $(E) = the neutron differential flux N = the atom density of the target nuclei (atoms /g)
A = the decay constant of the product atcm (sec"I). I If the sample is permitted to decay for a time t, between exposure and counting, then the activity when counted is I = A = N [/,o (E)$(E)dE] (1-e
-At t)i e-At* .
A " spectrum-averaged cross section" may be defined as
/,o (E)o(E)dE a* .
l
/,4(E)dE I and the integrated flux as
, = l $ = /,o (E)dE . Then l
=
~ / o (E)$(E)dE
/ a (E)$(E)dE = ,
I"$ (E)dE = e4
/,0 (E)dE 1
lI .. .
38 so that the activity A may be written as I - At
-At" A = Nc4(1-e i) e .
I The flux is then computed from the measured activity as A
,= ,
-At No(1-e I)e-At*
If it is desired to find the flux for neutrons with energies above a l given energy level, Ec , the cross section corresponding to this energy level is defined as ,l I I"o (E)o(E)dE c(E>Ec ) = ll l #"o(E)dE E c where
*(E>Ec ) " #E$(E)dE c
Then I
/"a (E)o(E)dE
- l /*o(E)4dE = ,
/ E$(E)dE c
/ 4 (E)dE c
l lE = a (E>Ec ) 4 (E>Ec ) l l and the activity A may be written as
-At - At l ll A = No(E>E c )4(E>E c )(I-* )'
- l In case that the neutron flux is not constant, the dosimeter activity at the time of removal from the reactor is A = No(E>Ec )+(E>Ec)C i
l I
39 I where J l j C= I f (1-e - AT) )e- A(T-t ) : I j =1 j J = number of time intervals of constant flux f) = the fractional power level during the time interval j T3 = the time length of interval j I t) = the elapsed time from beginning of irradiation to l l l end of interval j
'T = the time from beginning of irradiation to counting. l Then
$(E>E c ) " Nc(E E 5 c
This is the equation used to find fluxes based on surveillance dosimeter activations. The time intervals are taken as one month each and average power during the month is used for values of f. Calculations of the flux and fluence were made with the DECAY code. The reactor power history was supplied in a private communication (24) . The fluences can be changed to fluxes by dividing by the number of seconds 7 in 2.94 years which is 9.28 x 10 . These results are summarized in Table 4D as discussed earlier. Displacements per Atom (doa) Analysis One measure of neutron radiation damage is the number of times, on I the average, that an atom has been displaced during an irradiation. The number of dpa associated with an irradiation depends on the amount of energy I deposited in the material by the neutrons; hence depends on the neutron spec-trum and the neutron fluence. If the spectrum is constant over the duration I of the irradiation, then: I - dpa = f a d( )$( )dE = 1,y 0 1 (c }i 1$0 d 1 I .
l l I . 40
= the group-averaged value of the displacement cross section where (od }i l over i'th energy interval,
$4
= the group-averaged value of fluence per unit energy over the
- i'th interval, and AE j = the width of the i'th energy interval, E9) -E.9 For a coarse-group representation of 49 (E), the group-averages of ed(E) should be weighted averages where the ideal weighting function is the actual neutron spectrum 4(E). This however, is generally not known. A theo-l retical based weighting spectrum (25) , recommended by the ASTM, was used to collapse fine-group displacement cross sections for iron (25) into the coarse-group cross sections appropriate to the 22 group DLC-23 library. These cross sections were included as an input to the DOT computer code calculation and
'l dpa for iron was calculated as a function of thickness in the vessel wall. Displacements per atom values for the capsule and pressure vessel wall for various time periods are shown in Table 7. For the capsule center, the peak value is 8.5 x 10-3 dpa after 2.94 EFPY of operation. This compares with a value of 6.32 x 10-3 dpa at the vessel wall inner diameter. Values are also shown for 1/4 T and 3/4 T locations and for the end-of-life irradi-l ation time of 32 EFPY. No simple correspondence has been found as yet be-tween dpa and a particular change in a material property. However, dpa values
~
l provide a spectrum-sensitive index that may prove to be a useful correlation parameter. TABLE 7. DISPLACEMENTS PER ATOM (DPA) VALUES FOR 1, 2.94, AND 32 EFPY I Location 1 EFPY 2.94 EFPY 32 EFPY
-3 9.22 x 10-2 Capsule 263 Center 2.88 x 10 8.47 x 10-3
,I Inner Diameter of Vessel Wall 2.15 x 10-3 6.32 x 10-3 6.88 x 10-2 I At 1/4 T Location 1.34 x 10
-3 3.94 x 10-3 4.29 x 10~2
-3 -2 l At 3/4 T Location 3.98 x 10-4 1.17 x 10 1.27 x 10 lI
I I 41 I Thermal Monitors The capsule contained four types of low melting point eutectic alloy thermal monitors which were in the fonn of a helix. The helix was located below a stainless steel weight inside a quartz tube. Four thermal monitors, one of each type as indicated in Table 2, were placed in each of the three tensile-monitor compartments. The thennal monitors were examined at a magnification of about 4X using' a stereomicroscope for evidence of melting. In addition, photographs were taken of each group of four thermal monitors from a given compartment at a magnification of about 4X. These are shown in Figures 13A, 138, and 13C. Complete melting of the 536 F melting point alloy and partial melting of the 558 F melting point alloy thermal monitors was observed in all three compartments. This would indicate that the temperature was probably at 558 F during some portion of the irradiation. Since similar behavior was observed in all three compartments, it would indicate l that a relatively uniform maximum temperature profile was obtained during the irradiation. I II I i II l lI lI lI I
I I e, q, E a2 g :~;;gr7; f 't l! 1 ll r[ .4
.l
/-
8 {- t P l. [.)
- x. y
,. y < 2
,d , 1 df k .
.I l& ' . fR Yt : ll i
'/j c
g . a [ t I , i i. 'l l x
^ "
. ) ,
E m x ay _ 536F 558F 580F 590F FIGURE 13a. THERMAL MONITORS FROM COMPARTMENT N0. 4414 (TOP) I I
_L.. A _ .- -* I g m. 1 l ];g f 'I t' i ., I - 3 ! I .
~: ~
na; il .; i i l g 7- j;
-a . _
, .- y y lg
- ,} -fh
~;
q4 l 1 g - p 4 3 f j h .
%.{ . 3 .e 3
f 7:-
- 3. ! f
- g ] .
i !I j t
- I .
I o L 4 ; 'I j 1 l ~ g N
% ,- n .. . _3 536F 558F 580F 590F FIGURE 13b. THERMAL MONITORS FROM COMPARMENT N0. 4441 (MIDDLE)
I L- _ _ _. __
I I EA .- Q I ,y ; l ,.. 4' n
?
9 ,I %y,, - s a, e 1
% .-bIkh .4 ' , ,?
1 l e ;2 N a$l,
,f , A h,
g -
,p, , ,
l [ ' . '! dk K[ ijgl[ e ; Q]jy,
',.V \
,l [1"9 :g . y p ; y y4; .
;t 4 l h e
I I - I '
/
4 g . k c '.z
,t.
; L-536F 558F 580F 590F FIGURE 13c. THERMAL MONITORS FROM COMPARMENT N0. 4473 (BOTTOM)
I C
y 45 I Charpy Imoact properties I This section contains results and discussion pertaining to the Charpy impact testing. Appendix A contains further results and discussion relating to the instrumented procedures used during the impact testing. The impact properties determined as a function of temperature are listed in Tables 8 through 11. In addition to the impact energy values, the tables also list the measured values of lateral expansion and the estimated fracture appearance for each specimen. The lateral expansion is a measure of the deformation produced by the striking edge of the impact machine hamer when it impacts the specimen; it is the change in specimen thickness directly adjacent to the notch location. The fracture appearance is a visual estimate of the amount of shear or ductile type of fracture appearing on the specimen fracture surface. I The impact data are graphically shown in Figures 14 through 17. These show the change in impact properties as a function of temperature I for coth the impact energy (Figures 14a,15a,16a,17a) and the lateral expansion (Figure 14b,15b,16b,17b). Figures 18 through 21 show the I fracture surfaces of the Charpy specimens.
"'* '" **"'' '"* **"' ' " ""'* * '3 ""d 5 't-'b
'E5 transition temperature, the 35 mils lateral expansion temperature, and the upper shelf energy for the present program and for an earlier unirradiated !I i program. The upper shelf is defined as the average of three specimens ! tested above 95% fracture appearance. In the case of the HAZ material, the upper shelf was taken as the average of the two specimens tested at ! 100% fracture appearance. As indicated previously in the neutron dosimetry l section, the Charpy specimens received a fairly uniform exposure. The l neutron exposures for the three tensile-monitor compartments based on the average of the copper, iron, and nickel dosimeters ranged from 5.8 to 6.2 x 10 18 n/cm2 (>l MeV). Particular exposure values can be assigned to each of the four Charpy materials since specimens of a particular II
- I
'I I
'I 1 46 i 'I TABLE 8 CHARPY V-NOTCH IMPACT RESULTS FOR CALVERT I CLIFFS IRRADIA.TED BASE METAL, LONGITUDINAL ORIENTATION (PLATE D-7206-3) ll Test Impact lateral Fracture 3 Temp, Energy, Expansion, Appearance, 5 mils % Shear Specimen F ft-lb 147 0 8.0 10.4 5 ! 14C 40 20.3 20.8 10 142 60 28.7 29.2 15 14D 78 33.7 30.8 10 143 100 d6.0 43.0 30 144 115 50.2 44.8 30 145 130 69.8 61.8 35 14J 160 78.0 63.8 45 146 185 104.0 81.4 85 14E 242 120.5 92.2 100 l 148 300 113.0 92.4 100 14A 300 112.0 86.0 100 I 'I lI 'I I I - I I ,I
I I 47 I TABLE 9 CHARPY V-NOTCH IMPACT RESULTS FOR I CALVERT CLIFFS IRRADIATED WELD METAL I Test Impact lateral Fracture I Specimen Temp, F Energy, ft-lb Expansion, mils Appearance,
% Shear 34E -40 22.5 18.0 10 34L 0 24.4 24.4 25 34A 10 56.0 47.6 40 34C 20 38.2 34.2 35 34X 30 60.0 47.2 35 34J 30 50.0 43.6 35 347 40 68.5 56.6 55 341 78 78.8 62.7 75 34P 115 105.5 80.2 85 34B 185 120.0 90.2 100 34M 240 117.8 88.6 100 340 300 117.7 89.6 100 I
I I I I I I I I
I I 48 I I TABLE 10. CHARPY V-NOTCH IMPACT RESULTS FOR CALVERT CLIFFS IRRADIATED HAZ METAL I Test Impact Lateral Fracture Expt sion, I Specimen Temp. F Energy, ft-lb r4 s Appearance,
% Shear 43Y 40 16.5 17.2 20 44C 0 53.0 39.4 30 I 43U 44J 20 30 25.8 79.0 23.<
57.8 40 50 24.0 26.0 30 I d4A 43P 30 40 38.0 30.4 40 45.2 42.2 55 I 43T 60 447 78 53.2 45.0 55 446 116 68.7 56.0 65 I 44K 185 98.5 69.0 90 440 245 99.2 74.6 100 I 445 300 87.0 74.8 100 I I I I I I I ! I I
I I 49 I I TABLE 11. CHARPY V-NOTCH IMPACT RESULTS FOR CALVERT CLIFFS IRRADIATED STANDARD REFERENCE MATERIAL I Test Temp, Impact Energy, lateral Expansion, Fracture Appearance, I Specimen 64B F 40 ft-lb 6.0 mils 6.2
% Shear 5
644 78 11.7 12.6 5 1 64J 118 27.1 25.8 25 647 130 32.0 33.0 20 543 150 40.2 38.0 35 64C 170 50.2 46.4 35 645 185 59.2 51 .2 35 64D 210 69.1 62.4 50 64E 245 98.7 76.2 85 642 300 112.9 91.2 100 l 646 366 108.4 86.0 100 I 64A 366 107.0 85.8 100 'I I 'I lI I . I
mmmmmmmmmmmmmmmmmmmmmm E.
/
. /
/
/
~ -
(n - UNIRRADIATED 3I IRRADIATED / C '
/ ~
g / m . 5 / s b@ -
=- / -= 50 FT-LB SHIFT - 89 F -
/
30 FT-LB SHIFT - 60 F
/ .
/
/
en . i . i . i . i .
-180 0 188 288 300 400 i TEST TEMPERATURE: F i
FIGURE 14A. ENERGY VS TEMPERATURE FOR CALVERT CLIFFS , i UNIT NO. 1 BASE METAL LONGITUDINAL ORIENTATION PLATE NO. D7206-3. i i i
MD'(>, ////[9M) 9'f>+ . .e. .. <e
.T.ST TARGET (MT-3) 1,. %'t4 1.0 & 2 B34 y y DE I.I [,'8 lilM
!.f 1.25 1.4 1.6 4 6" 4 *> # + eb
+$f A)////
'4 4/+%g
; e 4///
9 99 YIIIQ '\
#+ IMAGE EVALUATION
$4%4 N
. TEST TARGET (MT-3) 1.0 5EEEM El0 E I.I L'" Ea la 1.25 1.4 1.6
< 6,, ,
#4 #
$ 4'
+$f Ax)/
// 'i<Q4 V. \ ,
W M M M M M M M M M M mmmmmmmmmmm l t I i N
.4 j e a
I / ! / l }
]o w
6 - - UNIRRADIATED IRRADIATED [ K
/ e -
- 2 -
m o
/
/ -
! $ S l a . / .
< = 35 MLE SHIFT - 82 F
] =7 e jh -
- /
i
~
/ '
l / e
- /
n . e . n . l i si
-180 0 100 200 300 400 l TEST TEMPERATURE: F FIGURE 148. LATERAL EXPANSION VS TEMPERATURE FOR
! CALVERT CLIFFS UNIT NO. 1 BASE METAL i LONGITUDINAL ORIENTATION PLATE NO. D7206-3. i
mmmmmmmmmm mmmmmm mmmmmm a m .
$ ~
- UNIRRADI ATED / -
IRRADIATED / (n / m / G - _ ti I E m M
- / .
/
$ - r-
/ c 50 FT-LB SHIFT - 54 F -
/
30 FT-LB SHIFT = 59 F ,
/
/
m . s . i . . . .
-289 -180 B 100 200 300 40s TEST TEMPERATURE: F FIGURE 15A. ENERGY VS TEMPERATURE FOR CALVERT CLIFFS UNIT NO 1 WELD METAL PLATES D7206-2/07206-1.
E. - , - s
- s,- -- s - , .
/
/ ~
m o
/
j -
- UNIRRADIATED g IRRADIATED [
s -
/ m -
8 l e
$m
/
fa x l 5 a .
< r = 35 MLE SHIFT - $iS F
/
$m
/ _
/
/ .
/
m - ' - ' - 8 - ' - ' -
-288 -188 9 100 200 300 400 TEST TEMPERATURE: F FIGURE 158. LATERAL EXPANSION VS TEMPERATURE FOR CALVERT CLIFFS UNIT NO. 1 WELD METAL PLATES D7206-2/D7206-1 .
f W M M MW M M M M M M M N mmmmm m e me i i - i - w - i i l i i , ~
~~~
~
s ' ' /
- UNIRRADI ATED /
l IRRADIATED / E _ / - _ f I m A 3 j g / g h - 50 FT-LB SHIFT - 102 F - ! / i m 1 ' / 30 FT-LB SHIFT = 94 F (De
/ .
/
/
g a f n i e I a f n I .
-208 -180 0 188 200 300 400 TEST TEMPERATURES F FIGURE 16A. ENERGY VS TEMPERATURE FOR CALVERT CLIFFS UNIT NO. 1 HAZ METAL PLATES D7206-3/07206-1.
- m m'~ W ~M
~
l M M M M M m, m M M m m ' 'm '"M m '~ m m " M ~m I e l 3 . , , , . , . , . ( l 'l .
- / ~
l - UNIRRADI ATED /
- [ . IRRADIATED -
g . 5 / l 2 *
/
- e h /
kE -
/
kW / e e m m m
= ! = 35 MLE SHIFT = 108 F
/ e h
$N -
/ e
/ m 7 -
m - i - ' - i - i - i - 200 -100 B 100 200 300 400 TEST TEMPERATURE: F FIGURE 168. LATERAL EXFANSION VS TEMPERATURE FOR CALVERT CLIFFS UNIT NO, i HAZ METAL PLATES D7206-3/07206-1. A.m - - - - - - - - _ _ . _ - - _ _ - - _ - - -
masemeee a m m as a sus e e a m 'm m ma m m i i - i - i -
/
/ .
/
- UNIRRADI ATED g IRRADIATED /
E" _.s
/
l
~ ~
g / jW$ - = /
/
c 50 FT-LB SHIFT = 107 F -
=
/
=/ 4 30 FT-LB SHIFT = 00 F
/
/
e - ' - ' - ' - ' -
-188 0 198 200 300 489 TEST TEMPERATUREr F FIGURE 17A. ENERGY VS TEMPERATURE FOR CALVERT CLIFFS UNIT NO. 1 STANDARD REFERENCE MATERIAL.
8
- ~~
/
- UNIRRADI ATED
/
IRRADIATED
]b -
/ -
E / g
~ ~
/
a l
< nn - -
% /
w J . ! _ y / O 35 MLE SHIFT - 94 F F j$ - / -
/
/
/
i G . 1 . t . t . 1 . l -les e les 200 see 400 TEST TEMPERATURE: F
- FIGURE 178. LATERAL EXPANSION VS TEMPERATURE FOR CALVERT CL.TFFS UNIT NO. 1 STANDARD
! REFERENCE MATERIAL. I (
! l i I ll I : Specimen Identification 147 14C 142 14D 143 144 h
/ ' ,' ']
;[
an;.k (lh-s
,a r..
E m *. m
,) .
,:p:,: y, .
~.?) .2- - ->
+
sv-vn 'R y ;
, ~, .
. +..
E t O 40 60 78 100 113 1 I Test Temperature, F 's i 's l I l Specimen Identification 145 14J 146 14E 14A 14B l3 2_- . r <.. ,1+ s/C *eNd > . M i,
.'1 - " 3 .L.L*. s-- '/,,-
~,8,gf;
, :- , ,5 3j[,4 y-- -
n. bn, ;c :., m
,fu
,l .n.- g n s a
..y,,, .
I 130 160 185 242 300 300 Test Temperature, F I FIGURE 18. CHAFPY IMPACT FRACTURE SURFACES FOR CALVERT CLIFFS CAPSULE 263, BASE METAL I I
il i I l l 'li l i i Specimen Identification 34E 34L 34A 34C 34K 34J I am Q ${j [ liI j. y$.p?Uh d;h.,. Q)j#t ,3 o. .m
$1?'kh$ ;f
- b If.g.: Nkh h"$:
i l :ggy '- e .-':. .. y : I, -40 0 10 20 30 30 ! Test Temperature, F lI t lI Specimen Identification i l 347 341 34P 34B 34M 34D 40 78 115 185 240 300 Test Temperature, F g I FIGURE 19. CHARPY IMPACT FRACTURE SURFACES FOR CALVERT CLIFFS CAPSULE 263, WELD METAL I i w ---..._---...-__.__._.____.___-...______-____--___________O _
,m
[ Specimen Identification 43Y 44C 43U 44J 44A 43P
.w
+c3 +~.y ,. q 9e su3 UIl e;.J g+; .. .,[') .3' x
.g,y r, ,
.- . n.[. . . .
9, . l Q' .,4 j;(. L 'r
-4C 0 20 30 30 40 Test Temperature, F i
1 Specimen Identification l 43T 447 446 44K 44D 445 y,.-:.y (: .- . .. .' . - .' . ' .
. ? * ;% .- .
- ": ' ; u ;n.,.
s .. g ) :
.~
~..,. t',;; - ; , ..... .
.. . . . .. . . ,, ; ~ t' 60 78 116 185 245 300 Test Temperature, F FIGURE 20. CHARPY IMPACT FRACTURE SURFACES FOR CALVERT CLIFFS CAPSULE 263, HAZ METAL
1 )I l \l 4 lI Specimen Identitication ! 64B 644 64J 647 643 64C 1 40 78 118 130 150 170 ( Test Temperature, F I I Specimen Identification 645 640 64E 642 646 64A
- . , . -t <
185 210 245 300 366 366 I Test Temperature, F FIGURE 21. CHARPY IMPACT FRACTURE SURFACES FOR CALVERT CLIFFS CAPSULE 263, SRM MATERIAL I I
~
I
I I
~
62 I TABLE 12.
SUMMARY
OF CHARDY IMPACT PROPERTIES FOR CALVERT CLIFFS UNIT N0.1 Upper 35-Mil Fluence, 30 Ft-Lb 50 Ft-Lb Shelf Lateral I Material Program n/cm2 (E > 1 MeV) Transition Temp, F Transition Temp, F Energy, Ft-Lb Expansion Temp, F Base L(a) Ref 10 0 8 42 138 20 I Base L(a) Present 6.0 x 10 68 111 115 82 l Weld Weld Ref 10 Present 0 6.1 x 10 I0
-50 9
-26 28 160 119
-40 15 l HAZ HAZ Ref 10 Present 0
5.9 x 10 IO
-85 9
-51 51 130 93
-75 31 SRM(b) Ref 10 0 39 62 135 46 SRM(b)
I Present 5.9.x 10 127 169 109 140 d I -- (a) Base metal, longitudinal orientation. I (b) Standard Reference Material. I TABLE 13. 50 FT-LB, 30 FT-LB, AND 35-MIL LATERAL EXPANSION TEMPERATURE SHIFTS AND DROP IN UPPER SHELF DUE TO IRRADIATION FOR CALVERT CLIFFS CAPSULE 263 I 30 Ft-Lb 50 Ft-Lb 35-Mil Lateral Drop in I Material Fluenge, n/cm (E > 1 MeV) Transition Temperature Shift, F Transition Temperature Shift, F Expansion Temperature Shift, F Upper Shel f, Ft-Lb Base L 6.0 x 10 18 60 69 62 23 18 I 6.1 x 10 55 Weld 59 54 41 18 HAZ 5.9 x 10 94 102 106 37 SRM 5.9 x 10 88 107 94 26 I
- I l I - .
I \\ material were all located near a given tensile-monitor compartment. The four Charpy materials received exposures estimated as follows: Base longitudinal 6.0 x 10 18 n/cm2 (E > 1 MeV) Weld 6.1 x 10 IO n/cm (E > 1 MeV) HAZ 5.9 x 10 18 n/cm (E > 1 MeV) SRM 5.9 x 10 18 n/cm2 (E > 1 Mey), The impact properties of the Calvert Cliffs base metal, weld metal, HAZ metal, and SRM metal are all significantly affected by irradiation, as can be seen in the figures of impact energy and lateral expansion versus temperature (Figur.:s 14 through 17). Table '3 is a comparison of the 30 ft-lb and 50 ft-lb transition temperature shifts, the 35-mil lateral expansion temperature shift and the l drop in upper shelf due to irradiation from the present program. The 50 ft-lb transition temperature shift is defined as the increase in the irradiated 50 ft-lb temperature with respect to the unirradiated 50 ft-lb temperature. The 30 ft-lb transition temperature shift and the 35-mil lateral expansion temperature shift are similarly defined. As can be seen, the greatest temperature shift occurs for the HAZ material in all three cases; however, the greatest drop in upper shelf occurs for the weld material. The reference temperature, RTNDT, was determined previously for the surveillance materials as described in Reference 7. The procedure for the determinatio the RT is defined by the ASME Boiler and NOT Pressure Vessel Code . The adjusted reference temperature for irradiated specimens can be determined using Appendix H, " Reactor Vessel Material Surveillance Program Requirements", to 10CFR50.(27) This temperature is then used in revising the plant pressure-temperature operating curves in 'I those cases where the fluence of the irradiated specimens is in the range to be experience ;y the pressure vessel. The adjusted reference tempe-I ature defined in Appendix H is determined by adding to the reference temperature the amount of the temperature shift in the Charpy curves I between the unirradiated mate.ial and the irradiated material, measured I I
'r I
I I I 64 l I at the 50 ft-lb level or at the 35-mil lateral expans. ion level, whichever temperature shift is greater. Table 14A presents the adjusted RT # NDT l the four materials contained in Capsule 263. For compariscn, the adjusted Rit DT was also calculated using revised ASTM 185-79 where the shift at l the 30 ft-lb level is used as the basis. As can be seen, the adjusted RT NDT is greater for all the materials except the weld material using l Appendix H criteria. The HAZ material has the highest adjusted RT of the three NDT l beltline region materials and is considered to be the controlling material. Therefore, it was used as the basis for the revised pressure-temperature l operating curves for the plant. Regulatory Guide 1.99, " Effects of Residual Elements on Predicted j Radiation Damage to Reactor Vessel Materials", was " ed to calcule.te the I l shift in the base, weld, and HAZ beltline materials for Calvert Cliffs Unit No. I based on the known copper and phosphorous contents as reported in Table 17 of the Chemistry Section which appears later in this report. The I , predicted shifts at the 50 ft-lb level were detemined using the fluence as assignec to ear.5 of the three vessel materials in the capsule. These values and the actual shifts obtained from the Charpy V-notch tests predicted for I the capsule are given in Table 148. As can be seen, the actual shift as ob-tained from the Charpy data is less than the predicted shift in each of the l three cases. The largest difference is in the case of the weld metal, which has an actual shift of 55 F compared to a predicted shift of 177 F. In addi-I tion, Table 14B also compares the percent decrease in the upper-shelf energy as predicted by Regulatory Guide 1.99 with the actual decrease observed for the base and weld materials. The percent drop in HAZ material cannot be pre-dicted by Regulatory Guide 1.99. As can be seen, the percent drop for both I the base and weld materials is less than that predicted by the Guide. A plot of fluence versus the 50 ft-lb transition shift for the base longitudinal, weld, HAZ, and SRM (where available) is shown in Figure 21 A for four Combustion Engineering plants. The plot shows the actual thifts as ob-tained from published Charpy data from surveillance capsule reports. It should be noted that ;?e Palisades pressure vessel is SA302 Grade B while the i
~
I I 65 I _ I TABLE 14A. ADJUSTED RTNDT VALUES FOR THE BELTLINE MATERIALS FOR cal, VERT CLIFFS CAPSULE 263 8 , Adjusted RT NDT Baseline (a) RT " Appendix ASTM NDT' Material 'p 30 Ft-Lb 50 Ft-Lb 35 MLE- H E185-79 ,I Base L Plate 07206 10 60 69 62 79 70 Weld Plates 7206-1/2 -80 59 54 55 -25 -21 4AZ Plates 07206-1/3 0 94 102 106 106 94 SRM 10 88 107 94 117 98 (a) The RT NDT as reported in Reference (10). TABLE 14B. PREDICTED AND ACTUAL 50 FT-LB TEMPERATURE SHIFT AND OROP IN UPPER-SHELF ENERGY FOR THE BELTLINE MATERIALS OF CALVERT CLIFFS UNIT NO. 1 I Shift in Reference Decrease in Upper-Temoerature Shelf Energy, percent Fluence, Predicted by Actual Shift Predicted by n/cm2 Reg Guide Obtained from Reg Guide t,apsule l Material (E > 1 MeV) 1.99 Capsule 263 1.99 263 Base L 6.0 x 10 18 73 69 18 16 18 34 26 Weld 6.1 x 10 177 55 HAZ 5.9 x 10 18 131 106 -- 39 i , 3 1
lI il il "
, other three vessels are SA533 Grade B. A trend band is drawn which shows suggested upper and lower bounding curves as a function of fluence for the j four plants. Note that the weld metal shift for Calvert Cliffs is substan-tially below the weld metal curve defined by the other three plants. This is probably because of the lower copper content of the weld metal.
Tensile Procerties I The tensile properties are listed in Table 15. The table lists test temperature, fluence, 0.2 percent offset yield strength, ultimate tensile strenjth fracture stress, fracture strength, uniform elongation, total elongatior, and reduction in area for the present program as well as for the unirradiated baseline program. Post-test photographs of the tensile I specimens are shown in Figure 22. These photographs show 'he necked down region of the gage length and the fracture. A typical tensile test curve I is shown in Figure 23; the particular test shown is for base metal specimen IJP tested at 550 F. I Tensile tests were run at 82 F, 250 F, and 550 F. The higher tem-perature tests generally exhibited a slight decrease in 0.2 percent offset I yield strength and a decrease in ultimate tensile strength for each material with respect to the room temperature tests. In general, ductility values I (as determined by total elongation and reduction in area) decreased slightly at higher test temperatures as compared to room temperature for each material. The one exception is that the total elongation for HAZ material increased slightly. The tensile specimens received fluences ranging from 5.8 to 18 6.2 x 10 n/cm2 (E > 1 MeV) as determined from the average of copper, iron, and nickel neutron dosimeters from each of the three tensile-monitor com-partments. When the tensile data for the capsule is compared to the unirra-diated baseline data as shown in Figures 24, 25, and 26, it can be seen that for a given test temperature, the yield strength and tensile strength increase. In general for a given temperature, the ductfiity of a given irradiated mate-rial decreases slightly with respect to the unirradiated material. However, in the case of the HAZ material there is very little change in total elonga- - tion from 250 to 550 F even though the reduction in area exhibits a normal decrease at all three temperatures. 1 I ;
1 ,, I . I 67 I I Q 8een Lonestudinal O= i l i I {}g 7 Ha* I 6 seu j I j {l I 500 J t calvert cliffs 4 m' Maine ; l i- Palisades - Yankee ! A 240 I I i i i 1'st Acc 4 l} j l Capsule i l; l I ~ I
-"~
400 Fort Calhoun f M ll j w-22s* j -yj ,
!I j j U i l
j 300 ---l,' y-4--- - - 7 -
. l <
l T l! I = 2m W! -
/ ,,,, b I l
4
,j l
j l! 1 lI 6 I
!! i . !
; e
, *0. ! !,
1 JV6 ;y l Trond Band I 100
---- - -f ,
iO j l ; ! I} I 0 1 x 1018 1 x 1019 1 x 1020 Fluence, n/ctn2 (E>1MeV) I I FIGURE 21 A. COMPARISON OF 50 FT-LB TRANSITION TEMPERATURE SHIFTS FOR FOUR :JMBUSTION ENGINEERING VESSELS Above data is for SA533 Grade B pressure vessel steel except Palisades where the vessel is SA302 Grade B. I I I I _ _.
BGl M M M M M M M M M M M <m W We M M M M M MM I TABLE 15.
SUMMARY
OF TENSILE PROPERTIES FOR CALVERT CLIFFS UNIT NO. I ") l Flue e, 0.2%(b) Ultimate Reduction Yield Tensile Fracture Fractur in Elongation Test x10 Specimen Temo, n/cm2 . Strength, Strength, Strength,(C) Stress,d) Area. Uniform, Total, - Ident. Material F (E>lHeV) ksi ksi ksi ksi % % % 0 70.6 93.9 - - 71.4 9.2 27.7
- Base L RT 25.8 Base L 82 5.8 79.1 102.0 63.5 195.6 67.5 12.1 IJA 70.7 9.1 24.0
- Base L 250 0 64.1 85.8 - -
5.8 73.9 95.7 66.0 184.2 64.2 12.1 21.9 14T Base L 250 9.3 23.3 Base L 550 0 65.7 90.7 - - 66.6 Base L 550 5.8 71.6 97.6 68.0 172.7 60.6 12.6 22.7 E IJP 0 74.7 88.5 - - 72.7 .0.0 29.0
- Weld RT 12.07 27.5 Weld 82 6.2 84.0 98.2 63.0 186.7 66.3 3K3 8.3 25.3 250 0 68.8 82.2 - - 72.8
- Weld 25.1 Weld 250 6.2 79.6 93.7 61.8 189.4 67.3 13.1 3K5 9.G 26.2
- Weld 550 0 66.9 84.7 - - 70.4 6.2 79.1 97.0 65.0 183.9 64.6 11.2 22.5 3K7 Weld 550 0 66.7 85.1 - -
73.0 6.8 26.0 llAZ RT 20.3 82 6.1 79.1 99.0 62.9 202.6 69.0 9.5 4KA HAZ 6.3 21.0 250 0 62.8 79.6 - - 74.4 IIAZ 22.3 250 6.1 72.7 92.3 59.7 191.6 68.8 11.1 4K6 HAZ 6.7 22.0 550 0 66.0 84.6 - - 67.3 IIAZ 22.4 iz.1 95.5 64.8 165.8 60.9 12.5 4K7 IIAZ 550 6.1 a Data for unirradiated tensile properties are aver 19es of values obtained from Reference 10. b Yield strength reported for unirradiated material is the lower value reported in Reference 10. c Fracture strength is the load at fracture divided by the original cross-sectional area. d) Fracture stess is the load at fracture divided by the final cross-sectiona: area.
I . . .
-{ #
y
.w
.. - +
p ?. ja;( c, ;. I <
'~1 ,.,.,,.
Material: Base Longitudinal Specimen: lJA N j?- Test Temperature: 82 F 5 _; < y,
,9. ,_
. i 4:9 ,
p: __ .
'I Material: Base Longitudinal 1( 37 w; ; _ ._
Specimen: lJT
- w , + w cq . . ' _ 4 g , "+ - -
Test Temperature: 250 F am . n-I ll , I Material: Base Longitudinal Specimen: lJP I . - Test Temperature: 550 F I . ._ ,,... .
-~ . - . ~ _ u
%g, I
,.,z. . Material: Held 1 <' " .- Specimen: 3K3
, ~j j " Test Temperature: 82 F I .
y --5:; x
~,-
%we ..
'"'-< e- g,j, ,
l I I sm;css
- a ,%
;W: '.
,4 w
m,. Material: Weld I 3, _
- . m :-.
1
;* - Specimen: 3K5
_' i.q l; Test Temperature: 250 F 2
. , ~p I : ' **%
- 5. ' 4 I FIGURE 22. POSTTEST PHOTOGRAPHS OF CALVERT CLIFFS TENSILE SPECIMENS FROM CAPSULE 263 I
I . l t er ure: 550 C l
'I em, 3-
= Material: HAZ c Specimen: 4KA Test Temperature: 82 F
.,-. ., ,' s m .; , ~. , s I
I v , s . r c
,y , -f ,._r -g Material: HAZ 7
~, Specimen: 4K6 Test Temperature: 2E0 F g
I w.
- p . , j~4 . _.
I g _ . . Material: HAZ Specimen: 4K7 Test Temperature: 550 F I
- I l
l FIGURE 22. (C0tiTIfiUED) lI I I_--
I 1 I l m I = . . . . . I . 5
~
I . I . g . I g f I 5 g$ - 'I E. I . E - ., g . I - I - B
.85
.1
. 15
.2
.23 STRAIN (IN/IN)
I FIGURE 23. TYPICAL STRESS STRAIN CURVE FOR CALVERT l CLIFFS UNIT NO. 1 CAPSULE 263. CURVE SHOWN IS FOR BASE METAL SPECIMEN NO. 1JP TESTED AT 550 F. g I ,I
I 72 4 ULTIMATE STRENGTH s' 's O$ . s ,___ 4 - g ~g_
*m ~ .
E N =
%f
. E s '
~~,_________e I m C -
8.2% YIELD STRENGTH l m 0 100 200 300 400 500 600 I s - -f3 UNIRRADIATED I LEGEND:
= = IRRADIATED I $ , . . . .
I a_------a _____y am I to - = . u REDUCTION IN AREA I 5 o=. I E d t g gm .
~~~~w_____---
5 TOTAL ELONGATION I g . . . . - I E 100 200 300 TEST TEMPERATURE (F) 400 500 602 FIGURE 24. EFFECT OF IRRADIATION ON THE TENSILE PROPERTIES OF CALVERT CLIFFS UNIT NO. 1 BASE I MATERIAL (PLATE NO. 07206-3). I
I l 73 I - - - - - ULTIMATE STRENGTH .
~
N_ : I a: s~ m 5 ' I e m g.
$ B I ff m
~ ~ B' '" - - - - - -
- -s E -
B.2% YIELD STRENGTH - l m 0 les 200 300 400 500 600 I s- - -O UNIRRADI ATED l LEGEND:
= = IRRADIATED I m m . . . . -
e-----&- _______g
= -
=
_m p I 6 e REDUCTION IN AREA m , - I l-- U 9 --__________e pm -
=
O" ~ . TOTAL ELONGATION O I m . . . . . 300 400 500 600 I B 100 200 TEST TEMPERATURE (F> I FIGURE 25. EFFECT OF IRRADIATION ON THE TENSILE PROPERTIES OF CALVERT CLIFFS UNIT NO. 1 WELD I MATERIAL (PLATE NO. D7206-1 /-2) .
ImmmmmmmM M M M M M M M M M M M M M M
?
8 m DUCTILITY (PERCENT) STRESS (KSI) m 0 20 40 60 80 50 60 70 80 90 100 110 fu p m . . . m . . zmm D$l ll 9 31 9 ~ 9 9 . gym 3 ; i @ f f yGH I i g I I r~o m I l I I n$' GE - 1 l - E - I I -
?o& 4 g
l Il 9 g l I I I y12 gi I iip UI mgo mm 1 J l ' I w I I *
~p
~
5Q$
*gg hE g gi l
ffi is gg b E g I i I I p d , OHz m I l > ~ l 1 J Z $ P i 5 ; i 1 g - n i mm mm E i i l$ 3
>fI ; a g s a ' ~ ~ '
iCH to z m E E l h j E l I e Qh di E lb 151 11 dl IB zg P g . . . g m m N
I 75 Chemical Analysis of Broken Charpy Specimens ,I Ten samples, five of each of the base longitudinal and weld mate-rials, were analyzed for copper (Cu), phesphorous (P), sulfur (S), vanadium (V), nickel (Ni), molybdenum (Mo), manganese (Mn), chromium (Cr), and sili- ,g
- g con (Si) using the method of x-ray fluorescence (XRF). The analytical results for the ten Charpy half samples are given in Table 16. Samples 17J (base longitudinal) and 34E (weld) were duplicated to provide an estimate of the precision. The results for the Mo, Cu, Ni, Mn, and Cr were obtained using a standard curve of the intensities as percent of the element in the standards.
The data for V, S, P, and Si were derived from ratioing the net intensities to a scattered radiation that was measured for each NBS standard and sample. For comparisoa, the chemical analysis of the surveillance test ' materials is reported in Table 17 for the same nine elements.(7) It can be seen that the XRF analysis reported in Table 16 is slightly different than l that reported in Table 17. For example, the copper content is always lower I and the phosphorous higher than that reported for the original test material. Even though there are differences in the XRF analysis, it is believed that l the analysis is comparable to that of the original test material. l l !I l l lI I I
I 76 I TABLE 16 RESULTS OF X-RAY FLUORESCENCE ANALYSES OF HALF CHARPY SPECIMENS FROM CALVERT CLIFFS UNIT NO. 1 CAPSULE 263 (Results in Percent by Weight) li Sample Material Si S P Mn Cr Ni Mo V Cu Base 0.35 0.03 .04 1.42 0.04 0.59 0.60 <0.01 0.09 14J (1) Base 0.32 0.03 .04 1.43 0.03 0.56 0.58 <0.01 0.08 14J (2) 142 Base 0.31 0.04 .04 1.39 0.03 0.60 0.58 <0.01 0.09 143 Base 0./.0 0.04 .04 1.40 0.02 0.58 0.53 <0.01 0.08 l 0.58 0.52 <0.01 0.05 l a- Base 0 33 0.03 .04 1.33 0.01 147 Base 0.26 0.04 .04 1.36 0.02 0.62 0.57 <0.01 0.06 AVG. 0.33 0.04 0.04 1.38 0.02 0.59 0.56 <0.01 0.08 l 1 34A Weld 0.50 0.04 .04 1.32 0.03 0.24 0.45 <0.01 0.15 l 34C Weld 0.26 0.02 .04 1.32 0.04 0.25 0.49 <0.01 0.12 0.22 0.03 .04 1.28 0.03 0.25 0.43 <0.01 0.12 34E(1) Weld 34E (2) Weld 0.25 0.03 .04 1.29 0.03 0.23 0.44 <0.01 0.12 34J Weld 0.25 0.02 .04 1.22 0.03 0.16 0.48 <0.01 0.17 347 Weld 0.35 0.04 .04 1.30 0.03 0.46 0.45 <0.01 0.15 AVG. 0.32 0.03 0.04 1.29 0.14 0.27 0.46 <0.01 0.14 Estimated 0.02 0.01 0.02 0.02 0.01 0.01 0.02 0.01 0.02 Detection Limit, " Cciculated 11.0 - - 2.0 - 6.0 2.0 - 8.0 Precision, I +% I I I
I . I 77 I l l I I TABLE 17. CHEMICAL ANALYSIS OF SURVEILL E TEST MATERIALS FOR CALVERT CLIFFS UNIT NO. 1 I Plate Comoosition. Wt ". Identification Si S P Mn Cr Ni Mo V Cu D7206-1 0.21 0.14 0.011 1.31 0.09 0.55 0.58 0.002 0.11 07206-2 0.24 0.14 0.011 1.28 0.08 0.64 0.67 0.001 0.12 07206-3(Base)(b) 0.24 0.16 0 011 1.29 0.08 0.64 0.69 0.001 0.12 j)(Weld)(c)0.20 0.013 0.014 1.05 0.06 0.18 0.55 0.003 0.24 j}(HAZ)(d) 0.18 0.013 0.014 1.20 0.06 0.19 0.56 0.003 0.18 I (a) Analysis obtained from Reference 7. (b) Base metal test material was fabricated from intermediate shell plate No. D7206-3. l (c) Weld metal test material was fabricated by welding together intermediate shell plate Nos. D7206-1 and D7206-2. l (d) Weld heat-affected-zone test material was fabricated by welding together intermediate shell plate Nos. D7206-1 and D7206-3. ,I I I I I - -- D
l 78 Development of Pressure-Temoerature Operating Curves for Calvert Cliffs Unit No. 1 Pressure-temperature curves have been develooed which are based upon the results of Charpy tests and surveillance measurements for the 263 degree wall capsule. The curves that have been prepared cover an addi-tional 5 EFPY of operation. Lacking specific plant data, values of 10 F and 60 psi were used for the measurement errors for reactor coolant tempera-ture and pressure respectively in preparing the curves. These values are believed to be conservative. The curves can be adjusted directly to incor-porate the measurement errors for the actual plant instrumentation if desired. Development of the P-T curves requires a knowledge of the neutron g fluences (E > 1 MeV) incident at the 1/4 T and 3/4 T wall positions and a method of predicting a shift in the reference temperature for nil-ductility transition (RTNDT) based on these fluences. The neutron fluence at the inner rad'us of the pressure vessel wall has been found to be 1.5 x 10 18 n/cm2 per EFPY. Also, the fluence at the 1/4 T position was calculated to be 0.574 times that at the inner wall and the fluence at +.he 3/4 T position was calculated to be 0.132 times that at I the inner wall. Using these results, a plot of n]utron fluence at 1/4 T and at 3/4 T as a function of full power years of operation was made. This is shown as Figure 27. From this figure, at 7.94 full power years, the fluence 18 incident at 1/4 T is 6.8 x 10 n/cm and the fluence incident at 3/4 T is 1.6 x 10 18 n/cm 2, The major results of the Charpy tests made on the specimen mate-rials irradiated in the capsule are shown in Table 18. The predicted RT NDT shifts were calculated from an expression relating shift to fluence (5.9 x 18 n/cm2 for E >lMeV) that is given in Regulatory Guide 1.99(28); 10 ART = 000 Mu - 0.08) + 200 @ - 0.008 NDT 1/2 l 1 x f/10 , I .
I I 79 I _ I
~
I - I _ ,,, I I 1019 I : I i x
~
'"TX I j _
I i I , ,0s. - I - I _ I I 1017 0 5 10 15 20 25 30 36 Time (Full Power Yeers) FIGURE 27. FLUENCE AT 1/4T AND 3/4T AS A FUNCTION OF FULL POWER YEARS I ,
I I 80 I I TABLE 18. SHIFTS IN RTNDT BASED ON RESULTS OF CHARPY TESTS I Unirradiated Measured Calculated (a) Material RT ART Cu P ART NDT NDT NOT Base L 10 F 69 F 0.12% 0.011% 73 F Weld -80 F 55 F 0.24% 0.014% 177 F HAZ 0F 106 F 0.18% 0.014% 131 F I (a) Calculated following Regulatory Guide 1.99. 'I I ll I I I I I l
I 81 Predicted shifts for two of the three materials are in reasonable agreement with measured results. The material exhibiting the largest nil-ductility transition temperature after irradiation is the HAZ material IO with a shift of 106 F at a fluence of 5.9 x 10 n/cm . A conservative estimate of the shif t in nil-ductility temperature as a function of fluence, which was used to generate the initial operating pressure-temperature curves, was given in the Technical Specifications and is reproduced as Figure 28. The present surveillance capsule result has been entered on this figure. A curve with the same functional form has been drawn which is normalized to the results for the HAZ material. This new curve can be used to estimate the shif t as a function of fluence. At 7.94 full power years, the shift is 113 F at 1/4 T where the fluence is 6.73 x 1018 n/cm2 and the shift is 30 F at 3/4 T where the fluence is 1.55 x 1018 n/cm2 . These shifts were used in calcu'.ating new pressure-temperature operating curves. Appendix G(29) presents a procedure for obtaining the allowable g loadings for ferritic pressure-retaining materials in Class I components. This procedure is based on the principles of linear elastic fracture mechan-ics. The calculational model developed is based on this procedure. The model uses the folicwing relation for calculation of heatup and cooldown curves for the reactor vessel: K;g > 2 KIM + KIT -
)
i Equation (1) can also be written as: KI R > 2 M, +M (2) t # max where K IR
= reference stress intensity factor l Mm = stress intensity index for membrane stress P = vessel pressure (psig)
R = vessel beltline mean radius (in.) l t = vessel beltline thickness (in.) 'I I L
I . 82 I I I l I -
/
I .
'E
- Dougn Curve I i
! 200
!1 I
Deseen Curve Normalized to HAZ hW l for Present Propam g i b ata D Point for HAZ Material From Present Program il 0 1018 i i i i i 1018 i i i i i 1020 Fluence, n/cm2 E > 1MeV g ,,ee. m ,vDeC1,u m 1....A1< ...C..A.. AS A FeNCTION OF FAST NEUT.ON FLUENCE (E>1 MeV) I I I ,I ' J
I
~
I 83 M = stress intensity index for thermal stress ai max = maximum temperature difference through the vessel l wall during heatup and cooldown. The reference stress intensity factor K;g is calculated using the I relationship given in Paragraph G-2110 of Appendix G which is: NDT
- X IR
= 25.777 + 1.223 e ksi Vin (3) where T = vessel plate temperature RT = nil-ductility temperature of the vessel beltline.
NDT This analytical approximation is based on the lower bound of static, dynamic, and crack-arrest critical K values g measured as a function of temperature on specimens of SA533B andSA5088 steel. It is assumed to be applicable to SA533B which is the structural material of the Calvert Cliffs pressure vessel. For determination of applicable pressure temperature relationships, the following must be detemined. (1) The location of maximum stresses during heatup I and cooldown. (2) The maximum temperature gradient in the reactor I vessel wall during heatup and cooldown operations. (3) The appl' 5ble values of Mm ""d M* t (4) The applicable pressure and temperature data avail-able to the reactor operator. Heatup and Cooldown Stress. For the case of vessel heatup, two I conditions were studied, the stresses at the 1/4 thickness location and the I 3/4 thickness location in the vessel plate. At the 1/4 thickness position, the themal stresses on heatup are compressive and the membrane stresses are tensile. Therefore, the most I highly stressed condition is when the themal stresses equal zero at an isothemal condition. Thus, the hypothetical case of an isothermal heatup, I O F/hr, is considered and applied to the heatup curves for conservatism. I I
I . I 84 At the 3/4 thickness position, the themal stresses and membrane stresses are tensile and therefore additive. As a result, the maximum thamal stresses for a particular heating rate are superimposed on the pressure I stresses in order to develop a conservative heatup curve. The most limiting of the two conditions is combined to develop con-I servative heatup curves. For the case of cooldown, the pressure calculations need only be I perfomed at the 1/4 thickress location since the membrane and themal I stresses are tensile and additive. The 3/4 thickness location will aliays be stressed to a lesser or equal value and thus need not be considered. Thermal Analysis. The temperature gradients in the pressure ves-sel wall at several heating and cooling rates were detamined by transient thermal analyses using the TRUMP (30) computer program. A description of the TRUMP program is presented in Appendix B. The pressure vessel wall was modeled as a cylinder having an internal diameter of 172.0 inches and a wall thickness of 8.63 inches. The pressure vessel wall was divided into 13 nodal elements. Relatively thin nodes were located at the inner and outer surfaces and at the 1/4, 1/2, and 3/4 wall thick-ness positions with thicker nodes between these positions. The inner nodal element was thermally coupled with a high thermal i coefficient to a boundary node whose temperature change was controlled at the desired heating or cooling rates. The outer surface of the outer nodal element and the ends of all nodal elements were made adiabatic surfaces, 1.6., no heat flow through these surfaces. Five heating and cooling rates were evaluated. These included 20, 40, 60, 80, and 100 F per hour. For each of the heating studies, the model
- was set at a uniform temperature 50 F and heated up to about 600 F. For each of the cooling studies, the model was initially set at a uniform temperature fl of 600 F and cooled at a constant rate to about 50 F. Temperature data were printed out at nine to fifteen time intervals during the transient depending f on the specific heating or cooling rate being evaluated.
Thermal conductivity data for Type 3A302 Grade B low alloy steel were taken from a U.S. Department of Commerce Report (31) and specific heat data l I
'I I lI were obtained for the TRPC Data Series (32) . Type SA533 Grade B low alloy steel is assumed to have the same properties.(33) I M and Mt . The stre intensity indices M and M are calculated m t 'g using procedures of Appendix G for the 1/4 T posit 9n. For the 3/4 T
- b position, methods of ASME Section XI were used to calculate the themal stress I
c mp nent. The factor Mt for a wall thickness of 8.63 inches is 0.4 ksi /in/F 5 taken from Figure G-2114.2 for the 1/4 T calculation. The factor M is jg 2.87 /in based on the curve of o/cy = 0.7 of Figure G-2114.1 which is con-E servative for both normal operating conditions and hydrotest operations. Temoerature and Pressure. The temperature used in the calculation is the temperature measured in the cold leg of the steam generator. This tem-perature is conservative since the actual reactor beltline temperature will be higher due to gamma heating effects and coolant flow path, or coolant
=T measured .
(4) Also, the instrument error of 10 F involved in the tanperature must be included in a conservative manner. Thus Equation (4) becomes: I T =T . (5) coolant measured-10*F The pressure, since it is measured in the pressurizer, must be cor-rected to the pressure at the bottom of the vessel beltline. This can be done by adding the head of water from the water level in the pressurizer to the I bottom of the beltline and the core pressure drop. The head is 21 psi and the core AP is lg psi. Also, the pressure measurement error of 60 psi must be included in a conservative manner: I P (6) RV =Pmeasured + 0 + 60 . A simple computer code was written to calculate the allowable pres-sure as a function of temperature during the heatup and cooldown operations I I
I i 86 I for both standard operating conditions and hydrotest conditions. The equa-tion used in this calculation for standard heatup and cooldown was: K I
- P measned
= 1000 -M[AT** 60 2N (7) mt which is the combination of Equations (2) and (6). For hydrotest conditions, the equation becomes:
P measured = 1000 60 . (8) h 1.5 M, Rt l The final form of Equation (5) for calculation of K IR during heatup was
- 4 I measured RTNDT + 160 - aTl/4 or 3/4) (9)
KIR = 26.777 + 1.223 e I and for cooldown I
- 49 I measured RTNDT + 160 + ATl/4 or 3/4) (10)
KIR = 26.777 + 1.233 e AT)f4 = the temperature difference between the inner wall surface and a point 1/4 of the way through the wall. AT3/4 = the temperature difference between the inner wall surface and a point 3/4 of the way through the wall. I The calculations required to develop the operating curves are sum-marized in Table 19. The results of the thermal calculations are given in Table 20. The temperature differences between the inner wall and the 1/4, 3/4, and total wall thickness are tabulated for all hest;p and cooldown rates. I I - I I
I I 87 TABLE 19.
SUMMARY
OF CALCULATIONS REQUIRED FOR OPERATING CURVES I Transient Rate (F/hr) Calculations Required Heatup 0 P @ 1/4T 20 P 0 3/4T 40 P @ 3/4T I 60 80 P 0 3/4T P 0 3/4T 100 P @ 3/4T Cooldown 20 P @ 1/4T 40 P 01/4T I 60 80 P @ 1/4T P @ 1/4T 100 P 01/4T I Notation: P - pressure calculation for normal operation. g 1/4 T or 3/4 T - location in the vessel plate. ,W I TABLE ?O. TEMPERATURE DIFFERENCES I :- Heatup Cooldown _ Temperature AT)j4 AT AT aT)j4 AT
' max 3/4 max 3/4 Change Rate I O F/hr 0 0 0 0 0 0 20 F/hr 6.3 13.3 14.2 4.4 9.5 10.1 40 F/hr 12.4 25.3 28.0 9.0 19.2 20.5 60 F/hr 18.2 38.6 41.1 13.9 29.8 31.8 80 F/hr 24.3 51 .4 54.7 18.5 39.6 42.2 100 F/hr 30.0 63.2 67.3 23.6 50.6 54.0 I
,I I I . . . -
I I 63 I The remaining input ^ a required for the calculations is: R = 90.31 inches t = 8.63 inches g' NDT..iitial = 0 F fted RT = 113 F @ 1/4T RThfted = 30 F @ 3/4T . Each calculation is performed for values of T measured from -200 F to 240 F in 20 increments. Intemediate values of K IR are printed to check the calculation. A copy of the printout is attached as Appendix C. This analysis is based on the technique I Critica_lity Conditions. described in the USAEC Regulatory Standard Review Plan Section 5.3.2.(34) The membrane stress for the reactor vessel beltline region is 3 , Pr , (2475 psig)(90.31 in.) = 52.9 ksi m t 8.63 in, where P = 1.1 Po= the inservice hydrotest pressure Po = 2250 psig = operating pressure. Thus, K; = 1.5 Mmm 3 = (1.5)(2.87)(25.9) = 112 ksi . Using Equation (9): shift + AT l/4 or 3/4 T = 142 + RTNDT + RTNDT The limit for core operation is then determined by drawing a vertical line I on the pressure-temperature curve; intersecting a curve 40 F higher than the pressure-temperature limit curve for heatup operations. I I . . .
I , I 89 The results of the calculations indicate that the 1/4 T position always limits the pressure-temperature region allowed during normal heatup and normal cooldown. During normal heatup the isothermal wall condition limits the pressure-temperature region allowed. This is shown in Figure 29. During normal cooldown, the pressure-temperature region allowed depends upon the rate of cooldown. A set of lin..' ct 'ves i'. shown in Figure 30. The allowable operating region in all cases is below a d to the right of the limit curve. The neatup curyc for noncritical operation, the hydrotest limit curve, and the limit curve for critical operation are shown in Figure 31. Cooldown curves for noncritical operation for cooldown russ of 20 F/hr and 100 F/hr and the limit curve for critical operation are shown in Figure 32. Also shown in Figures 31 and 32 are the Lowest Service Temperature limit line. This is based on the maximum RT NDT f all reactor coolant system pressure-retaining materials, with the exception of the pressure vessel, I which has been determined to be 50 F. Article NB-2332 of Section III of the ASME Boiler and Pressure Vessel Code requires the Lowest Service Temperature to be RTNDT + 100 F for piping, pumps and valves. Below this temperature, the system pressure must be limited to a maximum of 20 percent of the system I hydrostatic test pressure of 3125 psi. The heatup and cooldown limit lines for critical operation were I detennined as explained earlier. The minimum temperature for critical operation is I T = 142 + 113 + S1 = 285 F. The limit line at higher temperatures is just the none.ritical heating and cool-I down curves shifted by 40 F to higher teneratures. I I I I - I I
!I 90 'I ,400 I ! O F/hr(1/4 T) .I - 'I I I 1600 il 1I _ i
~
i 7, 1200 E E I i f 0 F/hr(1/4 T) ll "
- I 1
!I 40 lI t
il !I O O 40 80 120 100 200 240 290 320 360 Temperetute, F FIGURE 29. CALVERT CLIFFS UNIT . 9.1 NORMAL OPERATION HEATUP l LIMITS - 7.94 EFPY - HAZ METAL - RTNGT91/4 T = 113 F, RTNOT93/4 T = 30 F I
I I 91 2400 I I - I I 1600 I _.
! 1200 I '
I 800 I I O ,"o f M'Ol4 p fMt0I TI 1) p pg0l4II I 60 f M 5) go f M80 goo FM' U' 1 0 0 40 80 120 100 200 240 290 320 360 1 Temperature, F FIGURE 30. CALVERT CLIFFS UNIT NO.1 NORMAL OPERATION COOLDOWN LIMITS - 7.94 EFPY - HAZ METAL - RTNDT 91/4 T = 113 F, RTNDT 93/4 T = 30 F LI .- . -
I 92 I I i I ; l l 2400 Jg i o I 2000
.o I '
Hydro +est I Te E t 1* Critical Operation 1200 I !- .I Max Pressurs SDC Operation I 0 O 100 I 200 300 Temperature, F
,,oe...,. m 1u,co. .. _ ,.se1 m I
I I I I -. .- _ - --
1 n g :
)
I l
)
l I I
'I 2400 3.
I tI I I _ 3 ~! I s E 1600 2 s Critical OMration I C i 3290 I 800
<100 F/hr jI 400 <20 F/hr
/ Max Pressure 0
0 100 200 300 Temperature, F F cu m c-c-- Cu, , g
- I l
11 l I I. . . .
i 94 CONCLUSIONS l The evaluation of the dosimeters, thermal monitors, and mechanic.11 property specimens from Calvert Cliffs Unit No.1 Capsule 263 led to the fol-lowing conclusions-e The capsule received a maximum fast fluence exposure of 18 6.2 x 10 n/cm2 (E > 1 MeV). The capsule fluence leads the inner wall of the pressure vessel by a factor of 1.43. e The fast fluence exposure at the vessel wall for 32 EFpY I9 was determined to be 4.7 x 10 n/cm (E > 1 Me?) which results in a displacement per atom value of 6.9 x 10-2 (dpa). e The capsule did not exceed a temperature of 558 F as evi-denced from the examination of the 12 thermal monitors. e X-ray fluorescence analysis of base and weld metal broken Charpy specimens for nine elements including copper and phosphorous indicated that the chemistry was comparable to that run on the original test material, with only small variations. e For a given test temperature, the ultimate tensile strength y and 0.2 percent offset yield strength increased due to E irradiation. Conversely, the ductility generally decreased slightly due to irradiation. e The irradiation resulted in maximum shifts in the 50 ft-g 15 cr 35 mil lateral expansion temperatures for the base longitudinal, weld, HAZ, and SRM materials of 69 F, 55 F, 106 F, and 107 F, respectively. Based on the 10CFR50 Appendix H criteria, the limiting material for the beltline region was detennined to be HAZ. I
95 lI l e The shifts in the reference temperatures from the Charpy V-notch data for the three beltline materials were less than the predictions calculated from Regulatory Guide 1.99. Additionally, the actual percent drop in the upper-shelf energy is also less than that predicted from Regulatory Guide 1.99. e Heatup and cooldown limit operating curves were prepared l based on the 106 F shift in the HAZ material. Curves were drawn for the period of 2.94 to 7.94 EFPY of plant operation. These curves are conservative and no change in the node of plant operation is necessary before 7.94 EFPY. I I I I I I I I 5
I l 96 REFERENCES (1) Reuther, T. C. , and Zwilsky, K. M. , "The Effects of Neutron Irradia-tion on the Toughness and Ductility of Steels", in Proceedinas_of. Toward Imoroved Ductility and Toughness Symoosium, published by Iron I and Steel Institute of Japan (October,1971), pp 289-319. (2) Steel, L. E. , " Major Factors Affecting Neutron Irradiation Embrittle-ment of Pressure-Vessel Steels and Weldments", NRL Report 7176 (October 30,1970). (3) Berggren, R. G. , " Critical Factors in the Interpi atation of Radiation Effects on the Mechanical Properties of Structural :tetals", Welding Research Council Bulletin, 87, 1 (1963). (4) Hawthorne, J. R., " Radiation Effects Information Generated on the ASTM Reference Correlation-Monitor Steels", American Society for I Testing and Materials Data Series Publication 0554 (1974). (5) Steel, L. and Serpan, C. " Neutron Embrittlement of Pressure I E., Z., Vessel Steels - A Brief Review", Analysis of Reactor Vessel Radiation Effects Surveillance Programs, American Society for Testing and E Materials Special Technical Publication 481 (1969) pp 47-102. l (6) Integrity of Reactor Vessels for Light-Water Power Reactors, Report by the USAEC Advisory Committae on Reactor Safeguards (January, 1974). (7 ) Groeschel, R. C., Summary Report on Manufacture of Test Specimens and Assembly of Capsules for Irradiation Surveillance of Calvert Cliffs-I Unit-Reactor Vessel Materials, CE Report No. CENPD-34, (February 4, 1972). (8) " Surveillance Tests on Structural Materials in Nuclear Reactors", ASTM Designation E185-66 Book of ASTM Standards, Part 10. (9) Perrin, J. S., " Nuclear Reactor Pressure Vessel Surveillance Capsule Examinations: Application of American Society for Testing and Materials Standards", paper presented at the October,1977, International Atomic Energy International Symposium on Application of Reliability Technology F to Nuclear Power Plants (Reliability Problems of Reactor Pressure Comoonents) in Vienna, Austria, published in the Proceedings of the Conference. (10) Byrne, S. T., Biemiller, E. C., and Ragi, A., " Testing and Evaluation of Calvert Cliffs, Units 1 and 2 Reactor Vessel Materials Irradiation Surveillance Program Baseline Samples", CE Report No. TR-ESS-001, l (January 31,1975). l F (11) " Notched Bar Impact Testing of Metallic Materials", ASTM Designation ! E23-72, Book of ASTM Standards, Part 10 (1974), pp 167-183. j ~ k E
I 97 (12) " Determining Neutron Flux, Fluence, and Spectra by Radioactivation Techniques", ASTM Designation =261-77, Annual Book of ASTM Standards, Part 45. (13) " Determining Tnermal Neutron Flux by Radioactive Techniques." ASTM Designatier. E262-77, Annual Book of ASTM Standards Part 45. e
'14) "DetemiMng Fast-Neutron Flux by Radioactivation of Iron", ASTM Designation CE53-77, Annual Book of ASTM Standards, Part 45.
(15) " Determining Fast-Neutron Flux by Radioactivation of Nickel", ASTM Designation E264-77, Annual Book of ASTM Standards, Part 45. (16) " Measuring Fast-Neutron Flux Density by Radioactivation of Cooper, ASTM Designation =523-76, Annual Book of ASTM Standards, Part 45. (17) " Measuring Fast-Neutron Flux by Radioactivation of Titanium", ASTM Designation E526-76, Annual Book of ASTM Standards, Pcrt 45. (18) " Determining Fast Neutron Flux Density of Radioactivation of Uranium-I 238." 45. ASTM Designation E704-79, Annual Book of ASTM Standards, Part I (19) Perrin, J. S. , Fromm, E. 0. , and Lowry, L. M. , " Remote Disassembly and Examination of Nuclear Pressure Vessel Surveillance Capsules", Proceedings of the 25th Conference on Remote Systems Technology, American Nuclear Society (1977). (20) " Mechanical Testing of Steel Products", ASTM Designation A370-77, Annual Book of ASTM Standards, Part 10 (1979), pp 28-83. (21) RSIC Computer Code Collection, DOT 3.5-Two Dimensional Discrete <l5 Ordinates Radiation Transport Code, Radiation Shielding Information Center, Oak Ridge National Laboratory, Oak Ridge, Tennessee. 'E (22) RSIC Data Library Collection, DLC-23/ CASK, 40 Group Coupled Neutron l5 and Gama-Ray Cross Section Data, Radistic~. Shielding Infomation Center, Oak Ridge National Laboratory, Oak Ridge, Tennessee. (23) Private Communication, Lippold, W. J. , to Farmelo, D. R. , August 5, 1980. (24) Private Communication, Titland, L. E. , to Frorc, E. 0. , July 17, 1980. (25) Characterizing Neutron Exposures in Ferritic Steels in Tems of Displacements per Atom (DPA), ASTM Designation E693-79. (26) " Rules for Construction of Nuclear Power Plant Components", ASME Boiler and Pressure Vessel Code, Section III, American Society of Mechanical Engineers, (1974 Edition). I I
I I 98 I (27) " Licensing of ProddCtion and Utili:ation Facilities", Title 10, Code of Federal Regulations, Part 50, Appendix H, U.S. Government. (28) U.S. Nuclear Regulatory Commission, Regulatory Guide 1.99, " Effects of Residual Elements on Predicted Radiation Damage To Reactor Vessel I Materials". (29) ASME Boiler and Pressure Vessel Code, Section III, Appendix G, " Pro-tection Against Nonductile Failure". (30) Edwards, A. L., " TRUMP: A computer Program for Transient and Steady State Temperature Distributions in Multidimensional Systems", Lawrence Radiation Laboratory, Livermore, Report UCRL-14754, Rev. 2 (1968). l (31) " Tentative Design Basis for Reactor Pressure Vessels and Directly Associated Components", U.S. Department of Commerce, PS-151987, December, 1958. I (32) Touloukian, Y. S. , Power, R. W. , Ho, C. Y. , and Klemens , P. G. ,- The TPRC Data Series, Thermalchysical Procerties of Matter, Volume 1, Thermal Conductivity, Metallic Elements and Alloys, Purdue Research Foundation, June, 1972. (34) U.S. Atomic Energy Corm 11ssion Regulatory Standard Review Plan, Director-ate of Licensing, Section 5.3.2, " Pressure-Temperature Limits". (35) " Mechanical and Physical Properties of Steels For Nuclear Applications", ADUSS92-1625, Section 3, United States Steel, 525 William Penn Place, Pittsburgh, Pennsylvania,15230, fiay,1967. I I I I I I I I I
[ [ E F ~ [ [ [ APPENDIX A INSTRUMENTED CHARPY EXAMINATION [ [ [ [ [ [ [
.I I
APPENDIX A INSTRUMENTED CHARPY EXAMINATION I INTRODUCTION I The radiation-induced embrittlement of the pressure vessel of a commercial nuclear reactor is monitored by evaluation of Charpy V-notch I impact specimens in surveillance capsules. In a conventional Charpy I V-notch impact test, the infomation obtained for each specimen includes the absorbed energy, the lateral expansion, and the fracture appearance. I Curves of energy versus temperature and lateral expansion versus tempera-ture can be drawn for a series of specimens of a given irradiated material tested over a range of temperature. These curves, when compared to I similar curves for the unirradiated material, show the shift in behavior due to irradiation. The curves can be used to detemine the adjusted reference temperature, RTNOT, by establishing the shifts in temperature between unirradiatec and irradiated curves corresponding to the 50 ft-lb I energy level and the 35 mils lateral expansion level. I Additional infomation can be determined from a Charpy V-notch impact test by using instrumented equipment to perform an instrumented Charpy V-notch impact test. These tests provide time information in addition to the energy absorbed. The loads during impact are obtained by instrumenting the Charpy striker or tup with strain gages, so that the striker is essentially a load cell. The details of this technique have been reported previously.(1,2) I The additional infomation obtained from the instrumented Charpy test is the general yield load, PGY (plastic yielding across the entire cross section of the Charpy specimen), the maximum load, Pmax, the brittle
- fracture load, Pp , and the time to brittle fracture (see Figure A-1).
The area under the load-time curve corresponds to the total energy absorbed, which is the only data obtained in a normal uninstrumented Cnarpy test. The instrumented test, however, allows separation of the energy absorbed into (1) the energy required to initiate ductile or brittle fracture (premaximum load energy), (2) the energy required for ductile tearing (postmaximum I . I
I - I n-2 lI .I !I General Yield Load, P gy Maximum Load, P max
- I Brittle Fracture Load, Pp
- I '
/
I , t
- l 3
}
- I Pre Maximum-Load" Energy
- 1 Time to Brittle Fracture >
.I mme
'I ,. gg ,o . .. a.,_.Lo.e eoe,,,
I g Poe, B,,tt,_,,._. ..e,,, <I I FIGURE A-1. AN IDEALIZED LOAD-TIME HISTORY FOR A CHARPY IMPACT TEST I I I -_ --- _
I I A-3 I load energy), and (3) the energy associated with shear lip formation (postbrittle fracture energy), as shown in Figure A-1. I In a normal Charpy impact study, the energy absorbed is determined as a function of temperature to obtain the Charpy impact curve and the 30/50 ft-lb transition temperatures. The instrumented Charpy test also gives the information shown ta Figure A-1 as a function of temperature, as shown by the example in Figure A-2. Various investiga-tors (3-6) have developed theories that permit a detailed analysis of the load-temperature diagram. This diagram can be divided into four regions of fracture behavior, as shown in Figure A-2. In each region, different I fracture parameters are involved.II) Extended discussions of these fracture parameters can be found in the references indicated above. EXPERIMENTAL PROCEDURES The general procedures for the instrumented Charpy test are the same as those for the conventional impact test, and are described in the main text of this report. The additional data are obtained through a tairly simple electronic configuration, as shown in the schematic diagram of Figure A-3. The striker of the impact machine is modified to make it a dynamic load sensor. The modification consists of a four-arm resistance strain gage bridge positioned on the striker to detect the compression loading of the striker during the impact loading of the specimen. The compressive elastic strain signal resulting from the striker contacting I the specimen is conditioned by a high-gain dynamic amplifier and the out-put is fed into a digital oscilloscope. The load-time information is digitized and displayed on the screen of the digital oscilloscope. It is subsequently plotted on an x-y recorder. The load-time history as a function of test temperature forms the basis for further data analysis. The digital oscilloscope is triggered by a light beam device at the I correct time to capture the amplifier output signal. I I
-I
!I 1 l A-4 i
!I
!I !I
- i. s s
! s i N s l '%s { s N P,,, ! = N i = s F ! E i o l } Pp 5 %P gy
! .3 i
Y li ic. Region 1 Region 2 Region 3 Region 4 i ! Test Temperature I i l i
- FIGURE A-2. GRAPHICAL ANALYSIS OF CHARPY IMPACT DATA 4
- 1
!,I JI, il!
t
J e A-5 I I m ( a ) l 1
,I l (c l! ):
V Ml J Oscilloscope Bridge Balance I and O O Amplifier i I I Shunt Triggering Flesistance 0 ,,;c, I I I Hammer y I I - FIGURE A-3. DIAGRAM OF INSTRUMENTATION ASSOCIATED WITH INSTRUMENTED CHARPY EXAMINATION I I I I .
I I A-6 I RESULTS AND DISCUSSION I Specimens of four materials were tested. These materials are base metal longitudinal orientation, weld metal, heat-affected-zone (HAZ) I metal and standard reference material. The instrumented Charpy results are presented in Tables A-1 through A-4. The tables list the specimen I number, test temperature, impact energy, general yield load, and maximum load. The load time curves are presented in Figures A-4 through A-7. I It can readily be observed that the features of the load-time curves change as a function of temperature. The energy values listed in the I table are those obtained fram the impact machine dial. Each curve falls into one of the six distinctive notch-bar bending classifications shown I in Figure A-8. The pertinent data used in the analysis of each record r.re the general yield load (Pg ) and the maximum load (Pmax). The I load-temperature curves obtained for the four materials are shown in Figures A-9 through A-13. In general, the curves show both the general I yield load and the maximum load initially increasing as the temperature is decreased from the upper shelf region of the Charpy impact curve. As I the temperature is further decreased through the transition temperature region, the general yield load continues to increase. However, as the I temperature is decreased through the transition temperature region and into the lower shelf region, the maximum load is seen in a number of the I curves to go through a maximum and to then drop off sharply. I I l - I I I I I
I A-7
.I $ iABLE A-1. IriSTRUMEf1TED CHARPY IMPACT DATA 5 FOR CALVERT CLIFFS CAPSULE 263 BASE METAL I
Impact General Test Energy, Yield Maximum Specimen Temp., Ft-Lb Point Load Material Ident. F (Dial) Psy, Lb PMax, Lb Base L 147 0 8.0 3265 3265
- Base L 14C 40 20.3 2825 3970 Base L 142 60 28.7 2985 4210 Base L 14D 78 33.7 2780 4115 Base L 143 100 46.0 2510 4210 Base L 144 115 50.2 2905 4300 Base L 105 130 69.8 2545 4250 Base L 14J 160 78.0 2545 4240 Base L 146 185 104.0 2435 4240 Base L 14E 242 120.5 2385 4130 Base L 14B 300 113.0 2545 3955 Base L 14A 300 112.0 2325 3895 I
I I I I I I I
I I A-8 I I TABLE A-2 INSTRUMENTED CHARPY IMPACT DATA FOR CALVERT CLIFFS CAPSULE 263 WELD METAL I I Specimen Test Temp., Impact Energy, Ft-Lb General Yield Point Maximum Load Material Ident. F (Dial) P GY' Max'
-40 22.5 3155 4395 I Weld Weld 34E 34L 0 24.4 3015 4175 56.0 4460 I Weld Weld 34A 34C 10 20 38.2 2985 2985 4445 Weld 34J 30 50.0 2825 4350 I Weld 34K 30 60.0 2985 4445 68.5 2985 4390 I Weld Weld 347 341 40 78 78.8 2985 41,15 105.5 2670 4240 I Weld Weld 34P 348 115 185 120.0 2670 4210 117.8 2670 4100 I Weld Weld 34M 34D 240 300 117.7 2670 3955 I
I I I I I I I I
'I A-9 I I TABLE A-3 INSTRUMENTED CHARPY IMPACT DATA FOR CALVERT CLIFFS CAPSULE 263 HAZ METAL I I Specimen Test Temp., Impact Energy, Ft-Lb General Yield Point Maximum Load Material Ident. F (Dial) Pgy, Lb PMax, Lb HAZ 43Y -40 16.5 3815 3815 HAZ 44C 0 53.0 3220 4445 HAZ 43U 20 25.8 2905 3770 HAZ 44A 30 24.0 2825 4020 HAZ 44J 30 79.0 2935 4490 HAZ 43P 40 38.0 2825 4285 HAZ 43T 60 45.2 2670 4160 HAZ 447 78 53.2 2750 4190 HAZ 446 116 68.7 2670 4335 HAZ 44K 185 98.5 2510 4225 HAZ 44D 245 99.2 2435 4035 HAZ 445 300 87.0 2435 3845 I I I 'I I I .I I I -- - . . -
I - I A-10 l I TABLE A-4. INSTRUMENTED CHARPY IMPACT DATA FOR CALVERT CLIFFS CAPSULE 263 SFM METAL I Impact General Test Energy, Yield Maximum Specimen Temp., Ft-Lb Point Load I Material Ident. F (Dial) PGY, Lb PMax' L SRM 64B 40 6.0 2920 2920 SRM 644 78 11.7 2590 3330 SRM 64J 118 27.1 2670 4080 SRM 647 130 32.0 2545 4035 SRM 643 150 40.2 2560 4130 SPN 64C 170 50.2 2590 4240 l SRM SRM 645 640 185 210 59.2 69.1 2590 2510 4210 4130 l SRM SRM 64E 642 245 300 98.7 112.9 2385 2230 40e0 4005 l SRM SRM 64A 646 366 366 107.0 108.4 2355 2355 3800 3815 I (a) Standard Reference Material. I I I I I I I_
A-ll I 5222 l l l l l l SPECIMEN NO. : 147 TEST TEMPERATURE (F) : 0 4COU *
- DIAL ENERGY, (FT-LBS) : 8. 0 G ,
C 3220-- / - GENERAL YIELD LOAD (LB) : 32SS d f MAXIMUM LOAD (LB) : 32SS f + I Q s 2020+ f 1222-- -- l O l l l l l l l 0 520 1223 1522 2223 TIME (SECONDS X12E-S) 5220 l l l l l l l I SPECIMEN NO. : 14C TEST TEMPERATURE (F) : 42 42227 DIAL ENERGY, (FT-LBS) : 20. 3 G Q 3222-- -- GENERAL YIELD LOAD (LB) : 2826 d MAXIMUM LDAD (LB) : 3972 Q 2220-- -- s 1200- -- O I l l l l l l l 0 520 1220 1522 2223 TIME (SECONDS X12E-6) 5223 l l l l l l SPECIMEN ND. : 142 TEST TEMPERATURE (F) : 60 4000 ~~ DIAL ENERGY, (FT-LBS) : 28.7 G GENERAL YIELD LOAD (LB) : 2983 MAXIMUM LDAD (LB) : 4228 Q 2220-- -- I 3 1222- -- I 0 0 500 1020 1523 2000 TIME (SECONDS X12E-6) I g FIGURE A-4. INSTRUMENTED CHARPY IMPACT DATA FOR CALVERT CLIFFS UNIT l NO. 1 CAPSULE 263 BASE METAL LONGITUDINAL ORIENTATION. .I I.
I A-12 5222 . l . . SPECIMEN NO. 14D
.I TEST TEMPERATURE (F) : 78 4222+ +
DIAL ENERGY, CFT-LSS) : 33.7 G 3222+ + GENERAL YIELO LOAD CLB) : 2779 d MAXIMUM LOAD CLB) : 4113 Q c 2222-
+
J 1222- - I 2 l .
- r !
2 522 1222 1522 2222 I TIME (SECONDS X12E-d) I 5222 l l l . . SPECIMEN NO. : 143 TEST TEMPERATURE (F) : 122 4222+ + 0IAL ENERGY, (FT-LSS) : 46. 2 G
= 3222 + k --
GENERAL YIELD LCAD (LB) : 2512 d MAXIMUM LCAD (LB) : 4229 Q c 2222--
+
J 1222 - -- I 2 ' l 1 : . 2 522 1222 1522 2222 TIME (SECONOS X12E--6) 5222 : l l l l ! SPECIMEN NO. 144 4222 + TEST TEMPERATURE (F) : 113 -- l DIAL ENERGY, (FT-LBS) : 52.2 G
- C 3222+ +
I GENERAL YIELD LOAD (LB) : 2S25 d l MAXIMUM LOAD CLB) 4322 Q 2222 *- 0 J 1222- -- W 2 l l l l l l 2 522 1222 1522 2222 ,I I I TIME (SECONCS X12E-S) l l I FIGURE A-4 CONTINUED. I I .
I A-13 I 5222 l l l l ! l l SPECIMEN ND. : 145 TEST TEMPERATURE (F) 132 4222- - DIAL ENERGY, (FT-LBS) 69.8 G C 3222--
- I CENERAL YIELD LDAD (LB) : 2543 c MAXIMUM LOAD (LB) : 4239 Q 2222-- --
O 1222- -- I 2 I 2 l l 822 l l 1822 i . 2422 3222 TIME (SECONDS X12E-8) 5222 ,g l l l l l l l g SPECIMEN NO. : 14J TEST TEMPERATURE (F) : 18g 4222- - DIAL ENERGY, (FT-LBS) : 78.O G m 3222- - -- GENERAL YIELD LOAD (LB) 2543 d MAXIMUM LDAD (LB) : 4239 Q 2222 s 1922 ~ -- 2 l l l l l ' ; . 2 1222 2222 3222 4222 TIME (SECONDS X12E-6) 5222 l l l l l l l SPECIMEN ND. : 148 TEST TEMPERATURE (F) : 185 4222-- -- l DIAL ENERGY, (FT-LBS) 124.O G m 3222-I CENERAL YIELD LDAD CLB) : 2434 d MAXIMUM LDAD CLB) : 4239 Q 2222- -- S
^
1222- -- 2 l l l . l l l 2 2222 4222 8222 8222 TIME (SECONDS X10E-6) I l FIGURE A-4. CONTINUED. l l
A-14 5222 l l l l ! l ! SPECIMEN NO. : 14E TEST TEMPERATURE (F) : 242 4222-- - DIAL ENERGY, (FT-LBS) 122.5 G I m 5222- - -- GENERAL YIELD LOAD (LB) : 2388 d MAXIMUM LOAD CLB) : 4129 Q 2222- -- 3 1222- -- 0 l l l ! l l l 2 2222 4222 8222 8222 TIME (SECONDS X12E-6) i 5222 l l l l l l l SPECIMEN NO. 148 TEST TEMPERATURE (F) : 322 4222- - DIAL ENERGY, (FT-LBS) 113 G m 3222 - - t GENERAL YIELD LOAD CLB) : 2543 d MAXIMUM LOAD (LB) : 3956 Q 3 N22 [ 1222- - 2 l l l l l l l 2 2222 4222 8222 8222 TIME (SECDNDS X12E-6) 5222 l l l l l l ! SPECIMEN NO. 14A TEST TEMPERATURE (F) : 322 4222- - DIAL ENERGY, (FT-LBS) : 112 G m 3222 - -- GENERAL YIELD LOAD (LB) 2324 d MAXIMUM LOAD CLB) 3894 Q 2222- -- 3
' 1 1922- --
0 l l l . l l l 2 2222 4222 8222 8222 TIME (SECONDS X12E-5)
! FIGURE A-4. CONTINUED.
I
l A-15 5222 l l l l l l l SPECIMEN NO. 34E TEST TEMPERATURE (F) : -42 4222- - DIAL ENERGY, (FT-LBS) i 22.5 G
~ "
GENERAL YIELD L CAD CLB) 3156 MAXIMUM LCAD CLB) 4396 Q 2222- f --
-f I 3 1222--
n 2 : . : l : : : 2 522 1222 1522 2222 TIME (SECCNOS X12E-6) j 5222 i ! ! l l l SPECIMEN NO. : 34L TEST TEMPERA 1URE (F) : 2 4222 - DIAL ENERGY, (FT-LBS) 24.4 G m 3222- - -- GENERAL YIELD LCAD CLB) : 3214 d I MAXIMUM LOAD (LB) 4178 Q 2222-- O , I 1222-- " 2 : : : : : : :
- I 2 522 1222 1522 TIME (SECONDS X12E-O 2222 5222
- : :
SPECIMEN NO. 34A TEST TEMPERATURE (F) : Ig 4223- : " l DIAL ENERGY, (FT-LBS) : 58.O G C 3222- - GENERAL YIELO LOAD (LB) : 2983 d MAXIMUM LOAD (LB) : 4459 Q 2222-- - O I 1222 -- l 2 2 522 1222 1522 2222 TIME (SECONOS X12E-6)
! FIGURE A-5. INSTRUMENTED CHARPY IMPACT DATA FOR CALVERT CLIFFS UNIT NO. 1 CAPSULE 263 WELD METAL.
1 A-16 5000 l l l l l l l SPECIMEN NO. : 34C TEST TEMPERATURE (F) : 20 4000 " - DIAL ENERGY, (FT-LBS) 38.2 G I GENERAL YIELD LDAD (LB) : 2983 MAXIMLM LDAD (LB) 4443 C 3000-- d Q 2000- -- l 4 I I 2000- .. I O 0 l l 500 l l 1000 l l 1500 l 2000 TIME (SECONDS X10E-6) 5000 I l l l l l l l SPECIMEN NO. e 34J TEST TEMPERATURE (F) 30 4000-- - i DIAL ENERGY, (FT-LBS) : 50. O G m 3000- - -- GENERAL YIELD LDAD (LB) : 2828 d MAXIMUM LDAD (LB) 4349 Q 2000- -- 4 3 l 1000-- -- < k I O l . l l l . l 0 500 1000 1500 2000 TIhi (SECONDS X10E-6) < 5000 l l l l l l l SPECIMEN NO. s 34K TEST TEMPERATURE (F) : 30 4000 " " DIAL ENERGY, (FT-LBS) : 60. A G m 3000 ~ -- GENERAL YIELD LDAD (LB) : 2983 d MAXIMUM LDAD CLB) : 4443 Q 2000-- -- ] 1000- . 0 l l l l l l l 0 500 1000 1500 2000 i TIME (SECONDS X10E-6) ) I
, FIGURE A-5. CONTINUED.
- I
!I .. . - .. . . . . . .
I i A-17 5000 l l l l l l l I SPECIMEN NO. TEST TEMPERATURE (F) : 40 347 4000- - DIAL ENERGY, (FT-LBS) 88.5 G I GENERAL YIELD LOAD CLB) 2983 MAXIMUM LOAD CLB) : 4390 I Q 2000- 4 - 0 1000- - 0 l l l l . l l 000 1600 2400 3200 I O TIME (SECONDS X10E-8) 5020 l l l l ! I l l SPECIMEN NO. 341 TEST TEMPERATURE (F) : 78 4020 - DIAL ENERGY, (FT-LBS) : 78.O G G 3000-- -- GENERAL YIELD LOAD CLB) : 2983 d MAXIMUM LOAD (LB) : 4113 Q 2000-- -- s 1000- " O I l l l l ! l l 0 1000 2020 3000 4200 TIME (SECONDS X12E-6) I SPECIMEN NO. : 34P 5000 l l l l l l l TEST TEMPERATURE (F) : 115 4000- - DIAL ENERGY, (FT-LBS) : 105.5 G g m agggp I GENERAL YIELD LDAD CLB) : 2669 MAXIMUM LOAD (LB) : 4239 d Q 2000-1200- .. 0 l l l . l l l 0 2000 4000 6000 8000 TIME (SECONDS X10E-6) I I FIGURE A-5. CONTINUED. I , I --
I S200 l l l l l l l SPECIMEN NO. : 348 TEST TEMPERATURE &) 18S 4000- - DIAL ENERGY, (FT-LBS) 120. O G I GENERAL YIELD LDAD (LB) : 2669 MAXIMUM LDAD CLB) : 4208 C 3020-d Q 2000- - l 3 1000-
\
I O 0 l l 2000 l l 4000 l l 0000 l 8000 TIME (SECONDS X10E-6) SPECIMEN ND, a 34M TEST TEMPERATURE (F) : 240 4000" ' I DIAL ENERGY, (FT-LBS) : 117.8 GENERAL YIELD LDAD (LB) : 2669 G m 3000-d MAXIMUM LDAD (LB) 4098 Q ?000- . s 1000- -- O ; I l l l l l . 0 1000 2000 3000 4000 TIME (SECONDS X10E-6) 200 l l l l l l l SPECIMEN ND. 34D TEST TEMPERATURE (F) : 300 4000 " . DIAL ENERGY, (FT-LBS) : 117.7 G m 3000-I GENERAL YIELD LDAD CLB 2689 d MAXIMUM LDAD (LB) 39SE Q pygg., ,, I 3 1000- -- l 0 l l l l l l l t 8 1000 2000 3000 4000 TIME (SECONDS X10E-8) lI I FIGURE A-5. CONTINUED. I
I A-19 5222
- : ! ! l SPECIMEN ND. 43Y I TEST TEMPERATURE (F) : -42 4222 + -
- DIAL ENERGY, (FT-LBS)
- IS. 5 G
- C 3222-- --
GENERAL YIELD LDAD (LB) : 3815 d ! MAXIMUM LDAD (LB) 3815 Q 2222+ -- I s 1222 l 2 2 522 1222 1522 2222 TIME (SECDNDS X10E-6) I
- : l l l l l SPECIMEN ND. : 440 5222l g
TEST TEMPERATURE (F) : 2 4222 DIAL ENERGY, (FT-LBS) : 53 G I m 3222 + -- GENERAL YIELD LDAD (LB) : 32r9 d MAXIMUM LDAD CLB) : 4443 Q 2222-- -- s 1222 2 : ! ; ! : ! J 522 1222 1522 2222 TIME (SECDNDS X12E-6) I !! 5222 : : : : : : : l SPECIMEN ND. : 43U TEST TEMPERATURE (F) 22 42221 -- ( DIAL ENERGY, (FT-LBS) : 25.8 G m m 3C22-- -- ig GENERAL YIELD LDAD CLB) : 2925 d l MAXIMUM LDAD (L9) : 3788 Q 2222-- -- l l 1222-- -- l l 2 2 522 N 1222 : : 1522 2222 h g TIME (SECONDS X12E-6) I FIGURE A-6. INSTRUMENTED CHARPY IMPACT I DATA FOR CALVERT CLIFFS UNIT NO. 1 CAPSULE 263 HAZ METAL. I
I A-20 5000 i ,
' ' ' l l l :
SPECIMEN NO. : 44A l TEST TEMPERATURE (F) : 30 4000 - - DIAL ENERGY, (FT-LBS) : 24.0 G " GENERAL YIELD LOAD (LB) : 2825 MAXIMUM LOAD (LB) : 4019 Q 2200- -- I (l S 1220- - 4 l 0 0 l l 520 1000 1520 l 2000 TIME (SECONDS X10E-6) 5000 l l l l l l l I SPECIMEN NO. : 44J TEST TEMPERATURE (F) : 30 4000- - l DIAL ENERGY, (FT-LBS) : 79.O G l= m 3700- - l GENERAL YIELD LOAD (LB) : 2936 d MAXIMUM 8.0AD (LB) : 4490 Q 2000-- -- 3 1200-- -- O l l I l l l . . 0 520 1020 1500 2000 TIME (SECONDS X10E-6) 5020 l l l l l l l SPECIMEN NO. : 43P TEST TEMPERATURE (F) 40 4000-- DIAL ENERGY, (FT-LBS) : 38.O G m 3000- - -- I GENERAL YIELD LOAD CLB) : 2826 MAXIMUM LOAD (LB) 4286 d Q 3 2000--f I 1000-- O ! ! . ! ! O 500 1000 1500 2200 ' TIME (SECONDS X10E-6)
! FIGURE A-6. CONTINUED.
I I
I ' s' - c .
'I 500c l l l l l l l SPECIMEN NO. : 43T TEST TEMPERATURE (F) : 60 4000
DIAL ENERGY, (FT-LBS) : 45.2 G I 9 3000-- -- GENERAL YIELD LOAD (LB) : 2669 c MAXIMUM LOAD CLB) : 4161 Q 2000-- - I s 1000- - I 2 0
-' l 500 l l 1000 l l 1500 l
2000 TIME (SECONDS X10E-8) ! 5000 l l l l ; l l l SPECIMEN NO. : 447 , TEST TEMPERATURE (F) : 78 4000- -
~
DIAL ENERGY, (FT-LBS) : 53.2 G
"' m 3000- --
GENERAL YIELD LOAD (LB) : 2748 d MAXIMUM LDAD (LB) : 4192 Q 2000-- -- ! s 1989- - lq 0 l l l l . a l a see 1600 2400 3200
!E TIME (SECONDS X10E-6) 5000 l l l l l l l l SPECIMEN NO. : 448 TEST TEMPERATURE (F) : 116 4000- -
DIAL ENERGY, (FT-LBS) : 68.7 G m 3000 - -- GENERAL YIELD LOAD CLB) : 2669 d lI MAXIMUM LOAD CLB) : 4333 Q 2000-- --
- I
~
1000- -- fl 4 0 0 l l 800 l l 1800 l l 2400 l 3200 TIME (SECONDS X10E-6)
;g ;= FIGURE A-6. CONTINUED.
I I .
I A-22 5000 l l l l l l l 44K I SPECIMEN ND. TEST TEMPERATURE (F) : 185 4000" " DIAL ENERGY, (FT-LBS) : 98.5 G I GENERAL YIELD LDAD CLB) a 2512 MAXIMUM LDAD (LB) e 4223 G 3000-- d Q 2000-I I 3 1000- -- I O l l l l l . l 0 000 1800 2400 3200 TIME (SECDNDS X10E-6) 5000 I l l l l l l l SPECIMEN ND. 44D TEST TEMPERATURE (F) : 245 4000 ~ - DIAL ENERGY, (FT-LBS) e 99.2 G " " GENERAL YIELD LDAD (LB) : 2434 h MAXIMUM LDAD (LB) : 4035 Q 2000-- - s 1000- -- ' I O 0 l l 000 l l 1800 l l 2400 TIME (SECDNDS X10E-6) l 2200 , 100 l l l l l l SPECIMEN ND. : 445 TEST TEMPERATURE (F) : 300 4000 - - DIAL ENERGY, (FT-LBS) : 87.0 G m aggg. I GENERAL YIELD LDAD (LB) e 2434 d MAXIMUM LDAD (LB) 3847 Q 2000-- -- 1000- -- 0 l l l l l l . 0 800 1800 2400 3200 TIME (SECDNDS X10E-6) l I FIGURE A-6. CONTINUED. I I -- - .-
I I . A-13 5aes l l l l l I l l SPECIMEN ND. 648 TEST TEMPERATURE CF) : 4g 4888 - I DIAL ENERGY, CFT-LBS) : S. 2 GENERAL YIELD LDAD CLB) s 2922 G m 3288-d MAXIMUM LDAD CLB) : 2922 @ 2988-- -- S 1989- ; -- B . l l l l l I 0 500 1999 1588 2282 TIME CSECDNDS X19E-8) 5999 l l l l l l l --- I TEST TEMPERATURE CF) 78 4888 DIAL ENERGY, CFT -LBS) : 11.7 G m 3888- - -- GENERAL YIELD LDAD CLB) 2591 d I MAXIMUM LDAD CLB) : 3328 Q 2998-- S 1999-- ~ P l l l l l l l il 8 588 1998 1588 2289 5 TIME CSECDNDS X13E-6) M l l l l l l l SPECIMEN ND. 54J T7.ST TEMPERATURE CF) 118 4888 " D'AL ENERGY, CFT-LBS) : 27. 1 G 'I m 3898- - -- GENE 9AL YIELD LDAD CLB) : 2869 d MAXIMUM LDAD CLB) : 4882 S 2299-- -- I 3 1998- -- ( a l l . l l l l 2 588 1998 1589 2299 TIME CSECDNDS X19E-6) I l FIGURE A-7. INSTRUMENTED CHARPY IMPACT DATA FOR CALVERT CLIFFS UNIT l NO. 1 CAPSULE 263 SRM MATERIAL. I
I A-24 a, , , 5000
' ' - l l l ,
3PECIMEN NO. e 647
.I TEST TEMPERATURE (F) : ISO 4SSS" "
DIAL ENERGY, (FT-LBO 4 32.0 G I GENERAL YIELD LOAD (LB) i 2543 MAXIMUM LOAD CLB) 4035 m 3000-d Q 2000- -- I s 1020- -- I O P 0 l l 500 l l 1000 l l 1500 l 2000 TIME (SECONDS X10E-8) 5000 I l l l l l l l SPECIMEN NO. : 843 TEST TEMPERATURE (F) : 150 4000 - - DIAL ENERGY, (FT-LBS) : 40.2 G m 3000 - f - GENERAL YIELD LOAD (LB) i 2559 d MAXIMUM LOAD (LB) : 4129 Q 2000-- -- s 1000- -- '3 0 l l l l l l l S SSS 2SS" 25SS 2SSS 1 5 TIME (SECONOS X10E-8) 5000 l ! l l l l l . SPECIMEN NO. 64C TEST TEMPERATURE (F) 170 4000- - DIAL ENERGY, (FT-LBS) a 50. 2 G ie m 3000-- -
- E """"^' '' '^ S' ' 25$ d l
HAXIMUM LOAD (LB) : 4239 Q 2000-- -- [I 1000- - l l 0 0 l l 500 l l 1000 1500 l 2000 IS TIME (SECONDS X10E-6) l5
- I
! FIGURE A-7. CONTINUED.
I I
I I SPECIMEN ND. : 645 A-25 Sasa l l l l l l l TEST TEMPERATURE (F) 185 4000- - DIAL ENERGY, (FT-LBS) : 59.2 G lI GENERAL YIELD LDAD (LB) : 2591 MAXIMUM LDAD (LB) s 4228 m 3g20-- d Q 2220-- --
.I "
1000- --
; i i 0
2 800 1600 2400 3220 , TIME (SEODNDS X12E-6) 1 4 5202 l l l l l l l SPECIMEN ND. 84D i TEST TEMPERATURE (F) a 212 DIAL ENERGY, (FT-LBS) : 89.1 4000
] ""
m G m 3ggg.. .. GENERAL YIELD LDAD (LB) : 2512 d MAXIMUM LDAD (LB) : 4129 @ 2220- -- s 1000- -- 0 l l l l i . l t a 1220 2a20 Sass 4020 l TIME (SECONDS X10E-6) 5000 l l l l l l l SPECIMEN ND. 64E
- TEST TEMPERATURE (F)
- 245 4000" "
i DIAL ENERGY, (FT-LDS) : 98.7 G 4 m 3agg. . .. I GENERAL YIELD LDAD CLB) s 2388 d , MAXIMUM LDAD (La e 4082 S 2000-- -- I O 1000- -- [ B l l l l l l i'- l 0 1000 2200 3000 4022
= TIME (SECONDS X1EE-5)
,I 'I I FIGURE A-7. CONTINUED. I !I -- - .. __ -
I 5000 l l l l l l l SPECIMEN ND. e 842 I TEST TEMPERATURE (F) e Sag 4000- - DIAL ENERGY, (FT--LBS) i 112.9 G I GENERAL YIELD LDAD CLB) 2229 MAXIMUM LDAD CLB) : 4024 m 3000 d Q 2000-- -- l I s 1200- - I O 0 l l 1000 l l 2000 l l 3000 l 4000 TIME (SECONDS X10E-6) 5000 I l l l l l l l SPECIMEN ND. i 64A TEST TEMPERATURE (F) : 368 4000- - DIAL ENERGY, (FT-LBS) i 107. O G m 3000- - -- GENERAL YIELD LDAD CLB) : 2355 d MAXIMUM LDAD (LB) : 3799 Q 2000-- -- s 1000- -- I O l l l l l l ,- 0 1000 2000 3000 4000 TIME (SECDNDS X10E-6) 5000 l l l l l l l SPECIMEN ND. : 646 TEST TEMPERATURE (F) : 388 4000 - - DIAL ENERGY, (FT-LBS) 108.4 G " " GENERAL YIELD LDAD CLB) 2355 MAXIMUM LDAD CLB) 3815 Q 2000-- -- 1000- -- 0 l l l l l l l 0 1200 2000 3000 4000 TIME (SECONDS X10E-6) I FIGURE A-7. CONTINUED. I I . -
I I Fracture Type Load-Displacement Curves A-27 Raw Data Remarks I I I j P, Brittle fracture I I Deflection
'I I
11 a
) I I
P GY Brittle fracture I I Deflection i I lll 1 P gy Brittle fracture followed by fracture 3 indicative of shear lip formation Deflection l I IV P G Y, Stable crack propagation tollowed by l } 8 P max unstable brittle fracture and fracture indicative of shear lip formation Deflection l 'I V l g P gy, Stable crack propagation followed by C, P max fracture indicative of shear lip formation I Deflection l I VI
} P G Y, Stable crack propagation followed by
-J P max gross deformation Deflection FIGURE A-8. 'THE SIX TYPES OF FRACTURE FOR NOTCHED BAR BENDING I - . _ . - ..- - . . _ . .
1 a m m . i - i . i . l - 0PMAX ~ ! O Pgy A - - - _ r, m O
, s E
! o i ! E , o 1 >
-J k
~
E m - 0 . (n O O i O O O - t O g j E . . . i . i . l N g 100 200 300 400 TEST TEMPERATURE F l FIGURE A-9. INSTRUMENTED CHARPY LOAD-TEMPERATURE CURVES FOR CALVERT CLIFFS UNIT NO. 1 CAPSULE 263 BASE LONGITUDINAL ORIENTATION. l
jlll M M ,b ~ 0 M - - 0
~
- - 4 m
X E1 M A y M g R . P P UO 0O 0 TN M i c . 0 A 3 RT EI M PN MU E T M c - S DF AF 4 M 0F OI L
. 0 LLA i
2E CT
= R Y E M U PTM T RR A
R AED E HVL M - . P M CLE E AW T DC M e E 3 0T TR6 i . 0S NO2 1 E T EF M e e M E _ USL REU
- . TVS SRP e NUA g e I CC .
i 8 . 0 . 0 1 A s
- E R
U G 0 I 0 F 1 Eg eE4 3g mgN E3. ES lllI ll 1 ;!
mmmmmmmM M mmmmmmmmmmmmM 4
- m
- m G =
i ' i ' i ' ' , g l i O PgAx O U O Pgy
~
l 0 m OU 1
@ _ O _
v 9 0 m O tr:
~
l . . O 4 < 1 Q 8 ! ?"
@ 8 m _
O
~
W i e g __
. t . t . t . t .
1 N-100 0 100 200 300 400 TEST TEHPERATURE F ! FIGURE A-11. INSTRUMENTED CHARPY LOAD-TEMPERATURE i CURVES FOR CALVERT CLIFFS UNIT NO.1 j CAPSULE 263 HAZ METAL. 1 1
mm mm mm mm mm mm m m M m mM mm m m i I m E - i - i - i - i l OPMAX j O Pgy J O E D _ ' m - 4
, W 3
?
E _ m - en B
- m m B * ~
O m g . . . i . i . N 0 100 200 300 400 ~ TEST TEMPERATURE F FIGURE A-12. INSTRUMENTED CHARPY LOAD-TEMPERATURE CURVES FOR CALVERT CLIFFS UNIT NO.1 CAPSULE 263 SRM MATERIAL.
=-
i i Ig A-32 i l CONCLUSIONS !I l The instrumented Charpy impact test technique was used to obtain ! load-time information as a function of temperature for the Calvert Cliffs j pressure vessel mattrials. The general yield load was shown to increase as the temperature is decreased, with the maximum load going through a i maximum for the materials. il 5 i } j l } !I 4 4 !I E I I
~
I A-33 I AfPENDIX A REFERENCES I (1 ) Wullaert, R. Ts., " Applications of the Instrumented Charpy Impact Test", I in Impact Testing of Metals, American Society for Testing and Materials Special Technical Publication 466, p. 148 (1970). (2) Perrin, J. S. and Sheckherd, J. W., " Current and Advanced Pressure Vessel Surveillance Specimen Evaluation Techniques", Proceedings of 21st Conference on Remote Systems Technology, American Nuclear Society (1973). (3) Wilshaw, T. R. and Pratt, P. O. , "The Effect of Temperature and Strain Rate on the Deformation and Fracture of Mild-Steel Charpy Specimens", in I Proceedings of the First International Conference on Fracture, Sendai, Japan, September,1965, 2, p. 973. (4) Tetelman, A. S. and McEvily, A.J.R., Fracture of Structural Materials, John Wiley and Sons, Inc., New York (1967). ( 5) Knott, J. F. , "Some Effects of Hydrostatic Tension on the Fracture Behavior of Mild Steel", Ph.D. dissertation, University of Cambridge, Cambridge, England (1962). l ( 6) Fearnehough, G. D. and Hoy, C. J., " Mechanism of Deformation and Fracture 'g in the Charpy Test as Revealed by Dynamic Recording of Impact Loads", j Iron Steel Institute, 202, 912 (1964) l l I I I m u L
_ _ . a a ~ iA e am..- --D .- - 4_ _ lI l .I ! l
?
I I I I I
- APPENDIX B Description of TRUMP j I
il i I I ; l l l I I i I f l I
I I I APPENDIX B I Description of TRUMP I TRUMP solves a general nonlinear parabolic partial differential I equation describing flow in various kinds of potential fields, such as fields of temperature, pressure and electricity and magnetism; simultaneously, I it will solve two additional equations representing, in thermal problems, heat production by decomposition of two reactants having rate constants with I a general Arrhenius temperature dependence. Steady-state and transient flow in one, two or three dimensions are considered in geometrical configurations I having simple or complex shapes and structures. Problem parameters may vary with spatial positions, time or primary dependent variables--temperature, I pressure or field strength. Initial ccr.ditions may vary with spatial position; and among the criteria that may be specified for ending a problem are upper I and lower limits on the size of the primary dependent variable, upper limits on the problem time or on the number of time steps or on the computer time, 'I and attainment of steady-state. Solutions may be obtained by use of explicit or implicit-difference equations or by an optimized combination of both. I Solutions to steady-state and transient problems may be obtained. Geometric configurations may be quite complex, with flow in one, two or three I dimensions; with rectangular, cylindrical, axial or spherical symmetry; or with arbitrary snape and structure. Initial conditions may vary with spatial I position, time or the primary dependent variable (temperature, pressure, field strength). External sources or sinks, coupled to the system by means I of specified boundary conditions, may vary with time. Certain problem para-meters at one spatial location may be made to depend on the value of the I dependent variable at another spatial location, I I I I I
i l l I II \l 1 !I .I I i APPEfiDIX C l lI ! Computer Output for Operating and Hydrotest Pressure-Temperature Limits at 7.94 EFPY r lI lI i lI 11 !I il !I lI i lI 4 !I !I _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _
. - - _ c. } -. . -. .-- . .. - .. - - . . ..
SH OFERATING CURVES FOR CALVERT CLIFFS
===================================================
I ~~-~~ ~=~= =I F (CEGREES
~~ TRA NSIENT T YPE TRAK 51ENT RATE C TE D F/HR)'3/4~ T PO S IT ION ' ~ ~ ~ '
HE AT UP(NORMAL ODERA TION) ~ I ........... MEASUR50 TEMDED.TURE (F)
<(IR)
CALOULATED ARESSURE (PSI)
-67 0 27.6 356.7 t -47 0 27.8 363.1
-27.3 28.2 369.0 1 .
' ~ ~ ' ~ ~ ~ ~ ~ ~ ~ -"
-7.0 28.7 3 77.0 t 13 0 29.3 387.5 33.0 30.2 401.6 53.0 31.3 420 .5 2 73.0 32.S 445.7 93.0 34.8 479.4 S
113.0 37.5 524.5 D 133.0 41.1 584.6 153.0 46.C 665.0 O 173 0 52.4 772.4 O 193.0 61 1 916 0 213.0 72.6 1107.8 O 233.0 88.0 1364 1 0 253 0 136.6 1706 5 273.0 136.1 2164 2 0 -
' - - ~ 293.0 172.8 2775.7~
'~~ ~ ~ ~ ~ ~ ~ ~ - ~ ~ ~-~
' ~ ~ ~ ~ ~ ~
n 313.0' 221 9
~
3592.8 333.3 287.6 4684.7
~~
353.0 375.3 6143.7 Is E _ . . _ . . _ . _ . . _ _ _ ..__ ._. . . . _ _ . . . . .
C-2 SHIFTED OPERAT ING CURVE S FOR C A LVEF.T CLIFFS ,
============================ ========================
TRA NSIENT TYPE HE A T Up (N ORMAL OPERATION) ~~ ~ f- -
~ TRANSIENT RATE MEASURED
- 20. (DEGREES F/HR) 3/4 T POS! TION CALCULATEC
~ ~ ~ ~ " - PRESSURE (PSI) ~~
~
TEMPERATURE ~(F) <(IR)
-170 0 27.3 259.2
' ~
'- - 15 0'~. 0 27.4 261.9 i
-130.0 27.6 265.5 t -110.0 27.9 270.4
~
l , 276.9
-90 0 25.3 I ..
l _.
-70.L. _ . _ . . .26.3 285 7 l -50.0 29 6 297.3
~ ~ ~ ~ ~ ~ ~ ~ ~~ --" ~ ~ ~ ~
- '~ ~
-30.0 30.5 312.9
( - - - ~ ~ - - - " - _ig,g 31,7 333,7 10.0 33.4 361 4
-- ~ ~ ~ ~ ~ ~ ~ ~ - " ~ ----
35 6 -- ~ 3 9 6~.~6 --
' - ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ' ~50.0 35.6 448.2 70.0 42.6 514 5 r
le 110.0 55.1 721.5 J 64.6 $79 6 130.0 150.0 77.3 1091.0 L O 170 0 94.2 1373.4 r 190 0 116.9 1750.8 9 ~ ~ ~ ~~~~~ ~ "~ _ - . .2255.1
~ ~~ ~
~ ~ ~~" ~~
g 230.0 167.7 2929.0
~~'
L 250.G 241.d 3529.4
~ ~ ~ '
r 270.0 314.2 5032.6
.O O ..
L .. . ...
J .. __ ._ . - _ . _ C-3 . . . _ . . . _ . . _ _ ._ _ I0 - SHIFTED CPERATING CURVES FOR C ALVERT CLIFFS
======================================================
TRA NSIENT T YPE HEAT - TRAhSIENT' RATE ^~E3.~~~UP(NORMAL (CEGREES F/HR) 3/4 T PCS T:0N OPER ATION) ME15URED CALCULATE 3
~ ~
~~T E MPERE T URE- (F) ~~ K(IR)'~ ~~~ P RE SS URE (PSI)
I-
-170 0 27 2 165.9
~
-150.0 27.3 168.2
-130.0 27.5 171.2
-110.0 27.7 175.2 ,
-90.0 28.1 160.6
-70 0 '26.5 187.9
~
-50.0 29.1 197.5
~
-30.3 29.9 21C.4
~ ~~ ~ ~ ~
-10.0 30.9 227.6 10.G 32.3 250 6 30.0 .
34.1 281.4 50 0 36.6 322.5 70 0 39 9 377.4 -
~
~ ~ ~ ~ " ~ ~ ~ ~ ~
~~90.'C 4 C.~3~ 450 8 ~~~
110 0 SC.2 - 5 4 8 .~ 8 I' 130.0 58.1 679 8
~ ~
~ ' ~~ ~ ~ ~ ~ ~
150 0 68.6 ~S 5 4 .'9' 17].0 82.7 1088.8 193.0 131.4 1401 4 210.3 126.5 1819.1 230.0 160 1 2377.3 250.0 234.9 3123.1 270.0 264.8 4119.7 I . I _ .-. . .- . . I' -
--C_: . . -- -
l SHIFTED CFERATING CURVES FOP CALVERT CL: FFS
== = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = j
- TRa hSIENT .T YDE HEiT Uo(NORMAL OPER
- TION) l TRt.hS;ENT RATE 60. (CEGREES F/HR) 3/4 i POS! TION
! _ _ . . FEASURED . . . . . CALOULATED TE PERATURE (F) . _ _ _K(IR). _ . . _ _ _ PRESSURE (FSI) {
-170.0 27.1 77.6
-150 0 27.2 79.5 I
-110.0 27.6 65.4 90 0
-90.0 27.9
-70.0 26.2 46.0
-50.G 2c.7 1 08. 1 l
10.0 29.4 114.9
-10.0 3C.2 129.3 10.0 31.4 148.5 30.0 32.9 1/4.3 L 50.0 35.0 208.6 70.0 37.S 254.6 90.0 41.4 316.0 L 110.0 46.4 396.0 507.6 L 130 0 15~0. 6 53.0 6178 654.1 L ,-. -.... 190 0 .
69.2 1111 4 230.0 135.3 1927.9 250 0 175.8 2552.0 270.0 225.9 3385.8 I 6 I O w
C-5 . . -.. ... .. SHIFTED OPERATING CURVES F0F, O A LVERT CLI FFS
~
======================================================
T'i,1 N S! E *4T T Y P E HE AT Uo(NCRMAL CPE R ATION) TRANSIENT Rt.TE 80. (DEGREES F /HR) 3/4 T POS! TION MEASURED CALCULATED TEMPERSTURE (F) <(IR) PRESSURE (PSI)
-170 0 27.1 -13.8
-150 0 27.2 -12.3
-130 0 27.3 -10 2 i -110.0 27.4 -7.4 O . -- - -- - . --.. N .
27.7 .
- -.-90.0 -3.6
-70.0 25.0 1.4
-50.0 2 6 . f. 81 O -10.0 29.6 29 1 10.0 30.6 45 0 0 ---- -. _ _ _ _ - . - . -.
30 0 31.9 . - - - - . - - . 66.4 O 50 0 33.6 95.0 70.0 35.9 133.2 O.____._...._._......_.__-__- ._. 90 0 39 0_ _ _ - _ . . _ _ _ _iS4.2. . _ _ _ _ . _ _ _ _ _ . ._. e 110.0 43.1 252.3 130 0 4S.5 343 4 e 1 50.0 55.6 465.0 e 170.G 65.6 627.6 190 0 7S.7 644 9 O ~ - ~~ 1135.2'
~ ~ ~ ~ ~ ~ ~ '
210.'O 96.1 e 230.0 119.4 1523.2 250.0 150.6 2041 5 270.0 192.2 2734.2 Ir r E. - .
.g SHIFTED CDEATING CURVES F 0 C. C ALVERT CLIFFS
=======i.============================================
h 5
~~~
TRA N SIENT T YPE TR A NS;ENT R ATE 10 0.- HEAT UD (N OR MA L OPERATION) (3E3REES F/HR) 3/s T POSITION MEASURE 0 CALCULATED
~ '-
TEMPER TURE-~ (F) ~ ~ ~ <t:R) ~~ PRESSURE (PSI)
-170.0 27.0 -66.4 I4 -150.3 27.1
~
-97.1 ~ ~ ~ ~ ~
~ ~ ~ ~ ' ~ ~ ~ ' ~
-130.0 27.2 -95.3 I3 .
-110.0 27.3 -93.0 -
I3 -90.0 27.5 -89.8
-70.0 27.S -65.6 13
-50.0 25.1 -79 9 IO - - - - - -
3 0 '. 0^~ 2's .~6- - 72. 4
' - ~ ' - ~ ' - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
3 --' _10 0 29.2 -62 3 10 0 3;.0 -45 5 _3g_C_ 3,, , 3 C ,. _8_ __ _ I y-. .. . - _ ..- . . - . . 70.0 34.5 25.5 IO 90.0 37.0 66 4 IO 110.0 40.5 125.9 130.0 45.1 202.6 IO . _ . . . _ . . . _. _. _ IO 170.0 59.5 442.2 190.0 70.5 625.3 IO 210.0 35.2 ~~~ 870.0
~ ~ ~ ~ ~ ~ ~ ~
IO 230,0 104.9 1197.0 750.0 131.1 1633 9 IO ~~ 270 0 166.2 2217.6 \ O . . . _ . . . . .. .. l 1 0 - - .. . .. . - . _ . _ _. _.
C'I SHIFTED OFERATING CURVES F0F, C ALVERT CLIFFS
=====================================================
TRA NSIENT T YoE 000L C0 WN(NORMAL OPERATION)
~
~
TR A NSIENT R ATE' ~ 0. ~(DEGREES F/HR) 1/4 T POSITION MEASURED _ _ CALCULATE 0 TEMPER.TURE _(F) _ KtIR). PRESSURE (PSI)
-67.0 Ig -47.0 27.6 27.8 358.7 3 63. 1 -
-27.0 28.2 369.0 -
.770-
- ~ ~~
28 7 - '3'771 0' IO 13.0 29.3 387.5 33.0 30.2 401 6 O __ _ _ . . _ _ . . _ _ _ _ . _ . .. _. .__ _ ._. . _ _ _ _ IO 73.0 32.8 445.7 93 0 34.8 479.4 O _ IO 113.0 37.5_ . . . _ _ _ . _ 524.5. . _ _ _ _ _ . . _ _ _ _ . _ . _ _ . _ . 133.0 41.1 584.6 153 0 46.0 665.O O ~ - ~ ~ ~ ~ ' ~ 173.O 52.4 772.4 213.0 72.6 1107.8
- - ~ - ~ ~ ~ ~ - - '
233.0 88.0 1364.1 253 0 108.6 1706.5
= 273.0 136.1 2164.2
! 293.0 172.8 2775.7 i( 313.0 333 0 221.9 287.6 3592.8 4684.7 353.0 375.3 6143.7 1 . _ . _ . . . . . ___ _ . . _ _ _ . _ . . . _ _ . . . . _ _ _ _ _ .. _ . . . _ . _ . . . _ _ _ _ _ . _ _ _ _ . l l C . lr l
. - . - - - . - . _ _ _ - - - _ _ .. - _ c.g. . .- - ._ - -
SHIFTED CFERt.T I NG CURVE S FO,CALVERT CLIFFS
=====================================:==============
g ___ __ . T R t. N SI E N T T Y P E C O O L DO WN ( N 00t.L CPERATION) TR1NSIENT Rt.TE 20. as (DEGREES F/H:) 1/4 7 POSITION "E1SUREC CALCULATED I; TEMPERATURE (F) K(IR) PRESSURE (ASI) 1
...................................................... 1
-67 0 27.4 262.3 Id -67.0 27.6 292.3
~
-47.0 27.9 297 1 ,
-27.0 26.3 3C3.4
~~
22.S
~
311.S
~
-7 0 13.0 24.5 323.1 33.J 3;.4 336. 1 I. ._. . - ~ ~ ~
53.3 31.6 356.2
~ ~ ' ~ ~~
- ~ ~ --
I, 73.0 33.2 385.1 93.0 35.4 421 0 I -. 113.0 33.2 469 0 47.2 616.S I. _.___... _ .__153.3
.733.3 ._
173 0 __.34.1 _ _ _ _ . _ 213 0 75.6 1090 7 23K0
~ ~ ~ ~ ~
92.C
~ ~ - ~ ~ - ~ ~ ~
13 63. 9 - ~~ ~
._. --~
_. _~ 253.C"
~~ ~~
i~14 . C ~ ~ ~ ~ ~ ~ ~ ~1725.9 273 0 14J.3 2210 7 Ie ~~~~
~ ~ ~~293.0
~~
16 2. 5 - ~ 2868.5
~
I, 313.0
~ ~
'234.8- - ~ ~ ' - ~ ~3739 4
~ ~ " ~
333 0 304.7 A903.2 Ie . _ _ . _ . _ _ _ . . _ __ _ . - - - - . _ _ _ . . - . _ . - _ _ _ -_. Ie . . . _ . . . . . _. ._. i I .
U . . . . . SHIFTED OPERATING CURVES FOR OALVERT CLIFFS
..._____________________________________=========_===.
O TRakS:ENT TYPE 2 00L 30WN (NORMA L ODERATION) - TRANSIENT RATE 40. ~(JEGREES F /HR) 1/4 T POSITION ~ MEASURED CALCULATED O TEMPER:TURE (71' < < I R) eqEsSURE (PSI)
-67.0 27.5 2 20. 3
-67.] 27.7 224.1
~~
0 I -47 0
-27.0 26 0 25.4 229 1 235.9 . !
O I -7.0 26.9 244 9 l O 13.0 I 33.0 29.7 30.5 256 9 2 73.0 D I_ - - -
. . . - _ . . -5 3 .~ 0 ' ~ ~ - - ~31~. 9
~-
~
~
294.5
--~ ~
~ ~ ~ ~ ~ ~ ~
7 3.'~0 33.6 - ~ 323.'3
~ ~
~ ~ ~ ' ~ ~ '-
93.0 35 9 361 6
- - ~ ~
Ti3'.0
~ ~
-~
~ ~ ~ ' - ~- - ~~~ ~
~-39.9 ~4'i 2~.' 9 133.0 43.1 461.5 153 0 46.7 5 73.1 -
173.0 56 0 '695.5 ! 213 0 '9.' 1077.5 233 0 96.5 1369 5 253.0 12G.C 1759.7 273.0 151 3 2261 1
~~
~~~
293 0 193.2 2977.8
~
333 0 323.9 5152.8 353.C 423.8- 6815.0 y .
u ._ . . . . . _ . . . . . _ . . _ .. _ . . _ _ _ _. E I g SHIFTE3 OPERATING CURVES FOR OALVERT CLIFFS
========_= =========================================
TRi hS!ENT T YPE 000L CO WN (NORMA L OPERATION) I TR A NSIENT Rt TE ~ 60. (DEGREES F/HR) 1/ t. T POSITION
~~
HEASUREC ~~ CALCULATED g TEMPER:TURE ~ (F) K(IR) PRESSURE (PSI) I _..........______...______ .._________________________
-87 0 27.5 145.9
-67.0 ' - 27.7~ ~ ~ ~ ~ 150.O g -47.0 28.1 155.4 I -27.0 2c.5 1 62 . 7 ',
4 _ _ . . . . . _ _ _ _ _ _ . . _. _ _ _ _ . . _. _.-. . . . _ _ _ g 13 0 29 9 165.3 33 0 30.9 202.5
.-- __ . _.53.0 . - _ .._.
..32.3 _ _ . . . . _ _ _ _ . . 225.6. _ .
g 73 0 34.1 256.5
- 93.0 36.6 297.7 i
~ ~ ~ ' ~ ~ ~ ~ ~~
113.O 3'9W'~ ~ 3 52. 7
~ ~ ~ ~ ~ ^~
I 153 0 50.3 524.7 D _ . . _ . .. ._
. . _ . . . . _ . _ _ _ _ _173.0_ _ . . - _ . . 52.2. . . _ _ . - . .656.1. . _ _ _ _ _
l O 193 0 65.7 831 6 i i 213 0 82.8 1066.? D . . . _ _ . . - . . . . . - _ _ . 233.0 .101.7 1379.7. _ - - . . Q____.- 253.0 126.8 1 798.7. . _ . . . _ . . . 273.0 160 5 2358.4 gO . _ . . . _ _ .
. . .,0 2 0 5. C ~ ~~ ~-~ 310 6. 4
-- ~ ~ ~ ~ ~ ~ ~
O~ 313.0 265.5 4105.9 l 333.0 345.3 5441 4 353.0 453.0 7226 0 l I ._ . . _ _ . . - . _ . _ - . . _. - . . . _ _ . . I jO l jO - - . - - ._
C-ll
- e i SWIFTE3 0FERATING CURVE S FOR C ALVERT CL I FFS
======================================================
l TYPE C OOL COWN(NOR"AL OPERATION) D --"~~ ~ TRH T RSIENT A N S I E NT ~R A T E" ~ ~S 0 . ~~(DEGREES F/HR) 1/4 T POS
~
~~
MEASUREG CALCULATED g TEMPERA TURE '( F) ~' K(IR)' ~ ' ~ ~ ' ' P: ESSURE (PSI) l
-d7.C 27.6 77.6 O - . _ . . . . _ . .
-67.0 27.S.. . . . - - .81.9
-47 0 26.2 S7.7 Io -27.0 25.6 95.4 .
I - _.-7.0 29.2- . . . . . . ~ . . . 105.8 O 13.0 3c.1 119,6 33.0 31.2 138 1 iO .53.0 -
.. -- . 1 62. 7 32.7 O 73.0 34.7 195.7 93.0 37.3 239.7 IO O 133.0 45.6 377.3 153 0 51 9 482.4 IO 173.~0 -
~
60.3 622.8 ~
~ ~~~ ~
~ ~ ~ ~ ~
o
- ~ ~ ^
193.C 71.6 510.5 213.C 66.7 1061.3 iO 2 3 3 .~0 106.8 139~6-~4- ~ ~ -
'~ ' - ~ ~ ~ ~ ~ ^ 'O 253.0 133.7 1844 2 273.0 169.7 2442.6 O
I: 293 0 217.7 3242 1
~~~ ~ ~
O 313.0 282.0 4310.5
~
333.0 367.8 5738 1 l 0 . . _ - . . -- --- 353.0 . . . .. ._ . - - - - . . . . - .. 482.4
.-7645.7..
lO _ _ _ Io I. ._ _ _ _ - -
'- O
( .. - - . C-1
- = = == === = -
= = ============
g _ TR A N SIE NT .T Y PE C 00L D.0 hN (NOR M1L OPEP ATION) TRANSIENT RATE 100. (CEGREES F/HR) 1/4 T POSITION __ MEASUREC . _ _ . Ct.LOULATED t TEMPERATURE _(F) K(IR) . PRESSURE (PSI) I e
-67.0 27.6 .0
-67.0 27.9 4.7
{
-47.0 28.3 10 9 19.3
^
-27.0 26.5 ,
l . _ _ _ _ . - _ . _ _ . . _ . . . . _ _ . . . . _ - . . ( 13 0 3C.3 45.3 33 0 31 5 65.1 s . .-.-. - . - .. . ..- -. .-.. - _ . - -. .. .- .. 73.0 35.3 127.2 l' 93 0 33.1 174.6 113 0 41.9 , 238.0
, 133.0 47.0 322.7 153.0 53.8 435.9 213 0 91 3 1059 2 2 33-~0 iT370 14 ~2 C'.~ 1-- -- ~ ~~ ~ ~ ~ ~~ --"
~ ~ - - - ' ' ' - - ~
1
~ ~ ~
1902.2 ~
~ ~ ~ ~ ~ ~ ~ ~
- ~ ~ - - - ~ ~ ~ - -2 5~3 .~0 1Vi.9' 273.0 16 G . 7 2546.4 1
4 '~ - - ~~
~"'
293'.0
~ - ~ ~ ~ ~ ~
232.4~ 3407.3 '- ~
~~ ~ ~ ~ ~ ~
g 313.0 301.5 4557.7~ 333.0 393.9 6054.6 353.0 - - . .51 7.4. . - . . 6148.8 , I l - _ l
__ __________ _ . __ _C-13 SHIFTED OPERATING CURVES FOR CALVERT CLIFFS
-============================ =====_================= _
I TR A_NSIENT _ TYPE HYDR 0f w00L DOWN TRa hSIENT R ATE MEASURED 0. (DEGREES F/HR) ..1/4 T POSITION CALCULATED I T EMPERA TURE (F)
-87.0 K(IR) 27.4 PRESSURE (PSI) 507.2
-47.0 27.8 517.5
~
-27.0 28.2 525.4
~
-7 0 28.7 535.9 13 0 29.3 550.0 33 0 30 2 568.9 53 0 31.3 594.0 I 73.0 32.8 627.6 i
93 0 34.8 6 72.6 113.0 37.5 732.6 133 0 41.1 612.8 153.0 46.0 920.0 173.0 52.4 1063.2 193.0 61 1 1254.6 213.0 72.6 1510.4 233.0 88.0 1852.1
~~~
253 0 105.6 2306.7 273.C 136.1 2918 9 293 0 172.8 3734 2 313 0 221.9 4823.7 333 0 287.6 6279.5 353.0 375.3 e224.9 4 9 6 e. .m m-w' W}}