ML19242C919
| ML19242C919 | |
| Person / Time | |
|---|---|
| Site: | 07001100 |
| Issue date: | 06/27/1979 |
| From: | Lichtenberger H ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 7908140165 | |
| Download: ML19242C919 (20) | |
Text
C-E Power Systems Tel 203/GS8-1911 Comeustion Engineenng. Inc.
Telex. 99297 1000 Prospect Hdi Acad Windsor, Connecticut 06095 4
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l0 License SNM-1067 June 27,1979
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- 2 Docket 70-1100 U. S. Nuclear Regulatory Comission Washington, D. C.
20555 Attention: Mr. L. C. Rouse, Chief Fuel Processing & Fabrication Branch Division of Fuel Cycle & Material Safety Gentlemen:
This is in response to your request for additional information to support our amendment application dated April 23, 1979.
Resciution of NRC comments agreed to by Mr. N. Ketzlach c r your staff and Mr. G. J. Bakevich of my staff are forwarded as revised license pages. Please make the following page changes to our orignal amendment application:
Delete P6an Add Pages II-1, Rev. 2, 3/15/74 XIX-3, Rev. O, 3/22/79 XIX-3, Rev. 1, 6/27/79 XIX-6, Rev. O, 3/22/79 XIX-6, Rev. 1, 6/27/79 C-5, Rev. O, 3/22/79 C-5, Rev. 1, 6/27/79 C-6, Rev. O, 3/22/79 C-6, Rev. 1, 6/27/79 C-10, Rev. O, 3/22/79 C-10, Rev. 1, 6/27/79 C-18, Rev. O, 3/22/79 C-18, Rev.1, 6/27/79 C-19, Rev. O, 3/22/79 C-19, Rev.1, 6/27/79 C-19a, Rev. O, 6/27/79 D-2, Rev. O, 3/22/79 D-2, Rev. 1, 6/27/79 D-20, Rev. O, 6/27/79 D-21, Rev. O, 6/27/79 D-43 thru D-50, Rev. O, 6/27/79 Very truly yours, H. V. Lichtenberger Vice President-Nuclear Fuel Nuclear Power Systems-Manufacturing 00 HVL/GJB/ssb
~
Enclosures 13307 7908140\\
TABLE 19.1 Safe Individual Unit Limits for 5 4.1% enricsed U0 at optimum 2
moderation. All Mass and Volume limits adjus:ed to provide con-stant spacing areas for the enrichment shown. Heterogeneous limits have been developed with optimum rod sizes (up to 0.4" diameter) taken to allow for pellet chips, etc.
HOMOGENEOUS HETEROGENECUS Limit f*
Limit f*
Mass (Kg UO )
2
- 2.5 % U23s 54
.19 50
.26 2.5-3.0 41
.23 38
.29 3.0-3.2 36
.23 36
.29 3.2-3.4 35
.25 33
.29 3.4-3.6 22
.26 30
.30 3.6-3.8 28
.26 27
.29 3.8-4.1 24
.25 24
.27 Volume (liters)**
- 3.5%
31
.39 22
.40 3.5-4.1 25
.38 18
.38 Cylinder Diameter (inches)
- 3.5%
10.7
.34 9.5
.36 3.5-4.1 9.8
.33 8.9
.34 Slab Thickness (inches)
- 3.5%
5.1
.23 4.1
.14 3.5-4.1 4.6
.21 3.7
.13 Fraction of the equivalent unreflected critical spherical volume or mass.
Includes all available container volumes.
lf License No. SNM-1067, Docket 70-1100 Revision:
1 Date: 6/27/79 Page: XIX-3
4" Concrete D
U(3.5)02+H0 2
2 gm U/cc g
l y
10" Z = <25' N 7 l
l V
16" Concrete x, y This configuration has been evaluated using KENO with 16 group Hansen-Roach cross sections witi, the following critical parameters:
N x,y (cm) t/M Z
1 59.6 8.1 2
86.0 7.8 3
114.0 6.6 4
122.6 7.1 5
145.8 7.3 Accordingly, stacked units with at least 10 inch vertical separation, and no column exceeding 5 units, can be spaced with the area being increased by a mul-tiple equal to the number of units in the stack. To provide additional safety, stacked units will be limited to a maximum volume of 20 liters.
a (_ n b
t k
License No. SNM-1067, Occket 70-1100 Revision:
1 Date:
6/27/79 Page:
XIX-6
Criticality Safety Analysis The following conservative assumptions were incorporated into the calcu-lational model of the Virgin Powder Storage Area:
- 1) All steel structural materials were neglected.
containing
- 2) The fuel was assumed to be a homogeneous mixture of U0g 7.0 wt.% H 0.
2
- 3) The rack was filled to capacity (330 cans of UO2 powder) and ecch individual can was assumed to be full.
- 4) Effects of interspersed water moderation and flooding were not
' addressed.
The KENO-IV Code with sixteen group Hansen-Roach ross sections was used to determine the reactivity of the Virgin Powder Storage Area under the con-ditions noted above. Dimensional details of the model are provided in Secticn 1.1 of the demonstration section of this licensc.
Ak f 0.9338 : 0.0077 eff was obtained for an infinite system in the horizontal direction.
3.3 Batch Make-Up Pcwder containers are removed from the virgin powder storage area and placed on a conveyor (W.S. P-2) (safe cylinder limit) for transfer to the Batch Make-Up Hood (W.S. P-3).
A maximum of three powder containers are clamped to fixtures in the hood, where an appropriate batch of less than 35 Kg U0 is 2
weighed out and put into 5-gallon pails..The batch weights and enrichment are recorded on the container. A water tight cover is secured to these batch con-tainers and they are then conveyed (W.S. P-4) to a lift (W.S. P-5) for transfer to the blender hoods (W.S. P-6).
The batch make-up operation is enclosed in a ventilated hood. Sufficient negative pressure is provided to assure a minimum face velocity of 100 fpm.
Criticality Safety Analysis The following conservative assumptions were incorporated into the calcu-lational model of the Batch Make-Up Hood and associated conveyors (W.S. P-3 and P-4):
- 1) The 3 stainless steel UO p wder cans (safe cylinders) inside the hced were 2
considered to be fu'. at optimum moderation and maximum enrichment (J.1%
wt.% U235),
- 2) The 5-gallon batch make-up bucket inside the hood was assumed to con-tain UO2 pcwder at optimum mcderation and maximum enrichment (d.1 wt.%
U235),
License No. SNM-1067, Oceket 70-1100 Revision:
1 Date: 6/27/79 Page: Cc s
w
- 3) All structural steel in the hood was neglected.
- 4) All sealed containers of U0 n conveyors (W.S. P-2 and P-4) 2 adjacent to the hood were assumed to contain 7.0 wt.% H 0.
2 The KENO-IV Code with 16 group Hansen-Roach cross sections was used to determine the reactivity of the system ;nder various conditions of moderation.
Optimum moderatica of the fuel containers within the hood occurred at a fuel concentration of 1.8 gm U/cc in water, assuming no external mist. The highest reactivity of 0.7934 : 0.0070 for an infinite system (at 1.8 gm U/cc in water) occurred for the full flood case. Additional calculations for the external full flood condition were run for various concentrations of fuel in water ranging from 1.2 - 3.5 gm U/cc. The peak system reactivity of 0.8595 t 0.0117 for the flooded cases occurred at a fuel concentration of 2.6 gm U/cc in water. Dimen-sional details of the calculational model and results of the calculations are discussed in Section 1.2 of the demonstration section of this license.
3.4 Powder Preparation and Blendinc UO p wder frcm one sealed batch container (moderation control assurred) 2 is transferred to a blender where it is mixed with a binder (W.S. P-6).
Two separate blenders ter_d
- . mon powder spread funnel by means of individual powder transfer pipes entering at a 45 angle. An identical powder prep line runs parallel to this one at a centerline distance of 13 feet.
The blending operation is enclosed in a ventilated hood.
Sufficient negative pressure is provided to assure a minimum face velocity of 100 fpm.
3.4.1 Drying Aggicmerated UO powder is spread onto the dryer belt (W.S. P-7) from the 2
powder spread funnel to a controlled depth of 1/2". A complete enclosure is pro-vided around the dryer belt assembly and this enclosure is maintained at a slight negative pressure. The discharge end of the dryer belt utilizes a wiper blade to prevent the flow of significant amounts of material to the plenum under the belt. Nevertheless, this plenum shall be inspe:ted cnce per week and cleaned as necessary.
9;q
,1 (_
O License No. SNM-1067, Occket 70-1100 Revision: 1 Date:
6/27/79 Page: C-6
For the second case, the system was analyzed at 3.5 wt.% U235 with the 11" dia-meter, 40" long press feed hopper. The maximum k in the absence of external eff water mist occurred at 2.2 gm U/cc in water. This result was derived from cal-
~
values of 0.800 culations at 2.0, 2.2, and 2.4 gm U/cc with associated keff n.010, 0.833 : 0.014, and 0.804 0.014 respectively. Variable density external water mist was then introduced to determine peak reactivity of the system with the 11" hopper. Tha highest k of 0.934 0.017 occurred for the full flood eff case. This result was derived from calculations at 0.001, 0.01, 0.05, 0.10, and 1.0 gm/cc of H 0 with associated k values of 0.825 0.015, 0.821 0.020, 2
eff 0.805 0.012, 0.850 0.014, and 0.934 0.017 respectively.
Dimensional details of both calculational models and the results obtained for the 4.1% cases are discussed in Section 1.4 of the demonstration section of this license.
3.5 Final Mixir.g Filled press ~eed hoppers may be rolled to assure complete blending of the die lubricant (W.S. P-10).
s 3.6 Pressing The filled portable hoppers are transferred to the pelletizing presses (W.S. P-ll) and secured to assure their stability and the containment of powder.
Powder is gravity fed to the press, and compacted to green pellets which are placed into furnace beats. The boats have a maximum height of 3.7 inches. Only one boat shall be at each press at any one time.
Each press is provided a spacing area of at least 20 ft.
The press is provided with enclosures which assure adequate ventilation at the opening face, and at the junction of the portable hopper with the press. Air flow rates are sufficient to assure face velocities of at least 100 fpm.
Two work benches (W.S. P-12) are provided for inspection of pellets. These stations are limited to one safe mass each.
3.7 Dewaxing and Sintering Furnace boats containing green pellets are charged in a sinale line to a License No. SNM-1067, Occket 70-1100 Revision: 1 Date:
6/27/79 Page:
C-10 j}
7.0 PRETREATMENT OF LOW LEVEL LIOUID WASTES released to In order to effect a reduction in the quantities of UO2 the retention tanks in Building #6, low level liquid wastes, consisting primarily of floor mop water will be pumped into a 10 inch diameter,11 foot long settling tank with a release line located 18 inches from its lowest point.
The water is then passed through a high efficiency closed loop centrifuge system, sampled to verify acceptable discharge levels, and transferred to the retention tanks in Building #6. The settling tank is located in the rod loading area, and is shown as W.S. P-ll3 in Figu e C-i.
Based on past experience, wash water may contain up to 10-3uCi/cc (s0.5 gm U/t). Much of this activity quickly settles to the bottom of the tank.
Accordingly, criticality considerations are applied only to the lower 18 inches of the tank, with the balance of the tank considered to have a suf-ficiently low uranium concentration to preclude further criticality consider-ations.
Although the diameter of the tank (10 inches) slightly exceeds the Section 19 limit (9.8 inches), it is well below the minimum critical diameter (10.8 inches) for a fully reflected infinite cylinder.
In addition, the optimum concentration necessary to achieve criticality in a 10.8 inch cylinder is between 2000 and 2500 gm U/1, a factor of 4000 higher than the uranium con-centrations observed in the mop water handled. The volume of the settling tank is 23.2 liters. The allowable surface density (ta) is taken as 25% of the critical
, finite slab thickness (tc). Accordingly, ta = 1.38" or 3.26 liters /ft. The required spacing area for the tank is therefore 7.11 ft.
Sludge and other uranium bearing solids will be collected in volume limited SIU's.
This material may be subsequenti: loaded into trays to a maximum depth of 3.7 inches, dried in an oven (W.S. P-23 or 24) and stored in author-ized packages awaiting final disposition.
L License No. SNM-1067, Docket 70-1100 Revision: 1 Date: 6/27/79 Page: C-18 m
8.0 ROD LOADING AND ASSEMBLY FABRICATION 8.1 Pellet Alignment and Drying Pellets from the pellet fabrication facility, or from outside vendors are placed on a downdraft table (W.S.100) where they are loaded for place-ment into drying furnaces (W.S.101 and 102). On the table, the pellet con-figuration is limited to a 3.7 inch slab thickness. The U0 pellets are 2
placed on aluminum troughs in approximately 12 foot lengths before being loaod into the furnaces. The inside diameter of the furnaces is 20", and the overall length is 13 feet.
The furnaces are dry and about 12 inches above the floor level. 6ter m try is possible only when the doors at either end are open; however, under this condition, free drainage will occur. With the doors closed, the furnace is a sealed chamber and moderation control is assured.
Criticality Safety Analysis The following conservative assumptions were incorporated into the calcula-tional model of the pellet drying furnaces:
1)
It was assumed that the 200 pellet storage positions were fully loaded with maximum diameter pellets (0.3765") at maximum enrichment (4.1 wt.% U235),
- 2) The remaining 16 furnace locations contain B C powder clad in SS tubes 4
and fixed in place.
It was assumed that this powder was 45% of theoreti-cal density (although it " pours" to a greater T.D.).
The SS tubes have an
- 0. D. of 0.625 inch and a wall thickness of 0.035 inch. All SS tubes were omitted in the calculations for additional conservatism.
- 3) The furnaces were assumed to be infinitely long and spaced 36.5" on center.
An infinite array was assumed, although there are only two furnaces.
- 4) Variable density water mist was introduced to determine peak reactivity of the system.
- 5) All aluminum pellet troughs were omitted and the variable density mist was substituted in their place.
}
License No. SNM-1067, Docket 70-1100 Revision: 1 Date: 6/27/79 Page: C-19
- 6) Four grcup cross sections were generated using the CEPAK Code for the fuel and poison regions of the model and for the concrete floor and ceiling.
The KENO-IV Code was used to determine the reactivity of the Pellet Drying Furnaces under various external mist conditions with and without the fixed B C poison rods in place. The peak reactivity of the furnaces, keff "
40.8693 ? 0.0057, occurred for the full density water condition. Additional calculations were performed assuming loss of all poison. The margin of safety is unacceptable only for mist densities exceeding 50%. These conditions were not considered credible since the furnaces would drain freely to the floor and could not retain this amount of water.
Dimensional details of the calculational model and results obtained are presented in Section 1.7 of the demonstration section of this license.
/
~l
, 'i License No. SNM-1067, Docket 70-1100 Revision: 0 Date: 6/27/79 Page: C-19a
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3.0 VALIDATION OF CALCULATIONAL METHODS FOR NUCLEAR CRITICALITY SAFETY To validate the methods used in criticality analysis of fuel manufacturing processes, the 2.35 w/o U23s UO critical separation experiments by Battelle 2
(Reference 1) were analyzed in three dimensions. The mean k value of eff these nineteen experiments was 1.00157 with a standard deviation of.00419.
The experiments are concerned with the critical separation between water-flooded subcritical clusters of fuel rods in the presence of various fixed neutron poisons. The experiments were carried out in a 1.8m x 3m x 2.lm deep tank provided with features specifically designed and built for these experi-235U enriched UO ments. These experiments involved aluminum-clad 2.35 wt%
2 rods about 12mm in diameter by 914m in length. The critical separation be-tween three subcritical clusters of these rods aligned in a row was determined and analyzed with and without the following neutron absorber materials (neutron poisons) located between the clusters:
304L Steel with 0, 1.1, and 1.6 wt% boron; ard boral.
3.1 Description of Experiments The experiments analyzed each consisted of three assembly-like configurations separated by water and/or poison plates with the spacing adjusted to criticality.
Figure I illustrates typical top and end view of the arrangements. The 914mm length fuel rods ll.176mm in diameter of 2.05 w/o U235 in UO were clad with 2
6061 aluminum having an 0.D. of 62.7m and 0.762mm thick with different alloys of aluminum for top and bottom plugs. A fixed square' center-to-center pin pitch of 20.32m was maintained.
The number of pins in the width of the cluster varied (in different experiments) between 14 and 17 and the length from 20 to 24 pins.
The experimental data on experiments analyzed are given in Tables 1, 2 and 3.
/
0 f
License No. ShN-lC67, Docket 70-1100 Revision: 0 Date: 6/8/79 Page: 0-43
3.2 Method of Calculation The calculation methods wnich are essentially those used to determine reactivity for fuel rack storage, fuel shi,. ping containers plus other fuel configurations found in fuel manufacturing areas are based on CEPAK (Ref-erence 2) cross sections. Using an appropriate buckling value and taking proper account of resonance absorption, three fast groups are collapsed from 55 fine energy mesh groups in FORM and the one thermal group is col-lapsed from 29 thermal emergy groups in THER"05.
Fast cross sections for certain trace elements such as soitium and zine were obtained froa GGC-3 (Reference 3).
In addition, each component such as water gap, end plug, or poison plate has its thermal cross section determined by a slab THERMOS cal-culation employing the proper fuel environment.
Normally, for two dimensional representations, the transport Code DOT-IIW (Reference 4) is used.
Since, however, the short fuel length made necessary a three dimensional treatment, the Monte Carlo Code KENO IV (Reference 5) was used with six axial levels. Batches of one hundred neutron histories were used wt th the first four discarded. Calculated K values are shown in T?. ole eff 4.
For economy, about 150 batches were run for most cases, however, because of their greater use in fuel storage analyses, about 500 batches wc'2 employed for plain stainless steel and boral.
The mean value of the calculated k is 1.00157 with a standara deviation of effs
.00419; thus at a 95/95 confidence level using a o multiplier of 2.473, keff values are between 1.012 and 0.991.
2.3 Refere"ces:
1.
S. R. Bierman, E. D. Clayton and B. M. Durst, " Critical Separation Between SL5 critical Clusters of 2.35 w/o U235 Enriched UO Rods in Water with 2
Fixed Neutron Poisons", PNL-2438, October 1977.
2.
CEPAK--A Snythesis of the folluwing computer codes:
FORM - A Fa'.:rier Transf em Fast Spectrum Code for the IBM-7090, McGoff, D. 1.,.:AA-SR-Memo 5766 (September 1960).
THERMOS-A Thevrolization Transport Theory Code for Reactor Lattice Calculations, Honeck, H., BNL-5816 (July 1961).
License No. ;NM-1067, Dccket 70-1100 Revisten:
0 Date:
6/8/79 D 44 Page:
2/9 i[c
3.3 References (Cont'd)
CINDER - A One-Point Depletion and Fission Product Program, England, T. R., WAPD-TM-334 (Revised June 1964).
J. Adir, S. Clarke, R. Forelich, and L. Tody, " Users and Programn.2rs 3*
Manual for the GGC-3 Miltigroup Cross Section Code", GA-7157, July 25, 1967.
4 R. G. Sottesy, R. K. Disney, A. Collier, " User's Manual for the DOT-IIW Discrete Ordinates Transport Computer Code," WANL-TME-1982, December 1969.
5.
L. M. Petrie and N. F. Cross, " KENO IV, An Improved Monte Carlo Criticality Program", ORNL-4938, November 1975.
nn DU License No. SNM-1067, Docket 70-1100 Revision:
0 Date: 6/8/79 Page: 0-45
GRAPHICAL ARRANGEMENT OF S!MUt.ATED SHIPPING PACKAGE CRITICAL EXPERIMENTS f
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License No. SNM-1067, Docket 70-1100 Revision 0 Date:
6/8/79 Page:
D-46
TABLE 1 EXPERIMENTAL DATA ON CLUSERS 0F 7.35 wm
'U ENRICHED UO RODS IN WATER 2
FUEL CLUSTERS LENGTH x WI DTH CRITICAL SEPARATION 20.32mm 50. PITCH BETWEEN FUEL CLUSTERS (1)
(FUEL RODS)
(Xc, mm)
EXPERIMENT NUMBER 20 x 17 119.2 0.4 015 20 x 16 83.9 0.5 005
~
20 x 16 84.4 0.5 049 ( 2.)
22 x 16 (3) 100.5 0.5 013 20 x 14 44.6 1.0 021 (1} PERPENDICULAR ClSTANCE EETWEEN THE CELL BOUNDARIES OF THE FUEL CLUSERS. ERROR LIMITS ARE ONE STANDARD CEVI ATICC (2) RERUN OF E'<PERIMENT CC5 (3) CENER /UEL CLUSTER AT 20 x 16 RODS. TWO CUTER FUEL CLUSTERS AT 22 x 16 RODS EA s -
License No. SNM-1067, Docket 70-1100 Revision 0 Date:
6/8/79 Page:
D-47
TABLE 2 U ENRICHED U0 RODS IN WATER WITH 3NL STEEL PLATES EXPERIMENTAL DATA ON CLUSTERS OF 2.35 wl%
2 BETWEEN FUEL CLO TERS (1) 304L STEEL PLATES (2)
FUEL CLUSTERS DISTANCE TD CRITICAL SEPARATION LENGTH x W10TH 20.32mm 50. PiICH BORON CONTENT THlCKNESS FUEL CLUSTER (3) BETWEEN FUEL CLUSTERS (4)
(FUEL RODS) wt%
ap, mmi (G, mmi (Xc mm)
EXPERIMENT NUMBER 20 x 16 0
4.8510.15 6.45 0.06 68.8 i 0.2 02S 00h 20 x 16 0
4.85 0.15 27.32 0.50 76.410.4 20 x 16 0
4.8510.15 40.42 1 0.70 75.1'O.3 029 20 x 16 0
3.0210.13 6.4510.06 74.210.2 027 20 x 16 0
3.0210.13 40.42 1 0.70 71.610.3 026 20 x 17 0
3.02 0.13 6.45 0.06 IN.410.3 cx 20 x 17 0
3.0210.13 40.42 1 0.70 114.7 i 0.3 035
- s 20 x 17 1.05 f.98 i 0.06 6.45 0.06 75.610.2 032
.s 20 x 17 1.05 2.98 0.06 40.42 1 0.70 96.210.3 033
- V 20 x 17 1.62 2.98 t 0.05 6.45 t 0.06 73.6 i 0.3 038
.)
20 x 17 1.62 2.9810.05 40.42 1 0.70 95.210.3 039 (1) ERROR LIMIIS 5110WN ARE CNE STANDARD DEVIATION (2) PLATES ARE 356mm WIDE BY 915mm LONG.
(3) PERPEN0lCULAR'0ISTANCE BETWEEN THE CELL BOUNDARY OF THE CENTER FUEL CLUSTER AND THE NEAR SURFACE (4) PERPENDICULAR DISTANCE BETWEEN THE CELL BOUNDAP.!ES OF THE FUEL CLUSTERS
- To distinguist' from experiment #005 of Table 1.
License No. SNft-1067. Docket 70-1100 Revision 0 Date:
6'/8/79 Page:
D-48
TABLE 3 EXPERIMENTAL DArA CN CLUSTERS OF 2.35 wG U ENRIC[f9J0 RODS IN WATER WITH 50RAL PLATES 2
SERVEEN FUEL CLUSTERS (1)
FUEL CLUSTERS BORAL PLATES LENGTH x WIOTH DISTANCE TO CRITICAL SEPARATION 20.32mm 50. P!TCH THICKNESS (2) FUEL CLUS TER(3) BEri.EEN FUEL CLUSTERS (4)
(FUEL R005)
(tp, mm)
- 10. mmi (Xc mm)
EXPERIMENT NUMSER 20 x 17 7.13 0.11 6.45 x 0.06 63.4 t 0.2 020 IJ r 17 7.13 0.11 44.42 : 0.50 90.3 0.5 016 22 x 16 (5) 7.13 0.11 6.45 0.06 50.5 0.3 017 (1) ERROR LIMITS SHCWN ARE ONE STANDARD DEVI ATICN (2) INCLUDES 1.02 mm THICK CLADDING CF T/PE 1100 Al CN EITHER Silil_'0F THE 3 C-Al CCRE MATERI AL.
4 PLATES 365mm WICE SY 915 mm LCNC.
(3) PERPENDIC'ULAR DISTANCE SEri/EEN THE CELL SCUM 0ARY CF THE CEN!! R FUEL CLUSTER AND THE NEAR C'F THE SCRAL PLATE (4) PERPENDICULAR DISTANCE SEri.EEN TbE CELL BOUNDARIES CF THE f t;il CLUSTERS (5): ENTER FUEL CLUSTER AT 20 x 16 R005. Tito OUTER FUEL CLUS~ IRS AI 22 x 16 R005 EACH
. ' R,-,
License No. SNM-1067, Docket 70-1100 Revision 0 Date:
6/8/79 Page:
0-49
TABLE 4 Calculated keff ValJes Monte Carlo Expt #
Type Poison Plate Keff
((STD Deviation) 15 None 1.00227
.00534 04 None 0.99912
.00540 49
'None 1.00221
.00473 18 None 1.00813
' 00489 21 None 0.99589
.00461 28 304 S Steel 0.0 w/o Boron 1.00J93
.00308 05*
304 S Steel 0.0 w/o Boron 1.00329
.00303 29 304 S Steel 0.0 w/o Baron 1.00271
.00302 27 304 S Steel 0.0 w/o Boron 1.00418
.00273 26 304 S Steel 0.0 w/o Boren 0.99811
.00279 34 304 S Steel 0.0 w/o Boron 0.99793
.00297 35 304 S Steel 0.0 w/o Baron 1.00436
.00290 32 304 S Steel 1.05 w/o Baron 0.99970
.00524 33 304 S Steel 1.05 "/o Boron 1.01173
.00491 38 304 S Steel 1.62 w/o Baron 1.00289
.00512 39 304 5 Steel 1.62 w/o Baron 1.00208
.00506 20 Boral 0.99585
.00301 16 Boral 1.00020
.00288 17 Boral 0.99519
.00286 Mean Keff Value 1.00157 Std. deviation
.00419 n
e License No. SNM-1067, Docket 70-1100 Revision 0 Date:
6/8/79 Page:
0-50