ML20128C206
| ML20128C206 | |
| Person / Time | |
|---|---|
| Site: | 07105942 |
| Issue date: | 06/05/1985 |
| From: | Cunningham G GENERAL ELECTRIC CO. |
| To: | Macdonald C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 25349, NUDOCS 8507030506 | |
| Download: ML20128C206 (28) | |
Text
D
~
s GENER AL $ ELECTRIC Nd8 NUCLEAR F.NERGY BUslNEss OPERATIONS
(/'
GENERAL ELECTRIC COMPANY e VALLECITOs NUCLEAR CENTER e PLEAsANTON, CAUFORNIA 94566
- d, i
evi.
June 5, 1985 i
c,; kb&
=2s-
- e
Mr. C. E. MacDonald, Chief
'?
Transportation Certification Branch d
Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C.
20555
References:
- 1) Certificate of Compliance No. 5942, Docket 71-5942.
- 2) Application for Amendment to Certificate of Compliance No. 5942; May 30, 1985.
- 3) Application for Renewal of Certificate of Compliance No. 5942; May 30, 1985.
Dear Mr. MacDonald:
On May 30, 1985, General Electric requested an additional loading for the Model 700 shipping container (Ref. 2).
General Electric wishes to supersede that application with the following proposed Section 5.(b)(2)(viii) to read:
(viii) 3,510 gm U-235 provided the fuel is in the form of MTR-type fuel elements with each element containing no more than 351 gm U-235 and inserted in a spaced stainless steel fuel shipping basket described in GE Drawing No. 10604150, Rev. O.
A shoring device to limit vertical motion of the fuel elements will be included.
This request is supported by the attached criticality safetgnalys s.
Anapplicationfeecheckfor$150.00hasbeensubmittedwitheMay 30, 1985, request (Ref. 2).
g g
g 2-m application (Ref. 3) for Certificate of Compliance No. 5942);TeneM Please add any action taken in regard to this request to our E9 2
5 Sincerely, F
6w
- h. {. [
3 4
G. E. Cunningham Senior Licensing Engineer
$7e' g
/ca 5
JUN 111985 > E 2,
t;VSS S
- Att, u m sten n
%}
,"1 6*
DOCKET CLERK g
3 b
- gg
%g
- +
g-ga7ogeo..se.o,-
M 0710 2
C
CRITICALITY EVALUATION A criticality evaluation of the General Electric 700 cask is given below.
This cask has a cavity that is 15 inches in diameter by 54.75 inches long for holding material, including special nuclear material.
The cask is of steel-encased, lead-shielded construction.
If two casks are side by side, a minimum of at least 21.875 inches edge-to-edge separation is provided between the contents of one cask from the contents of the other.
6.1 Discussion and Results Compliance with 10CFR71.40 for Fissile Class III shipments is demonstrated below for one loading.
This loading involves 10 MTR-type fuel elements in which the elements are inserted in a stainless steel basket in a cask.
The basket provides a fixed neutron poison for each fuel element.
Each fuel element has 18 plates containing 19.5 grams U-235 of fully enriched uranium per plate.
Each fuel element also contains two aluminum support plates.
This gives 351 grams U-235 per fuel element and 3,510 grams U-235 per cask.
The contents of the cask during shipment are dry.
After the accident mentioned in 10CFR71.33.40, the contents of the cask are assumed to be wet.
Also, for loading and unloading activities for which hot cells are not available, the loading and unloading may be accomplished under water.
After an underwater loading is com-pleted, for example, the lid is placed on the cask and the cask is removed from the water; then the water is drained from the cask.
In the discussion below, details of the package fuel loading are presented first.
Then a description of the models used to calculate the k-effective values for the fuel loading is presented.
This is followed by the criticality calculation discussion for each of the models.
Finally, the criticality benchmark experiments section is presented.
1
c 6.2 Package Fuel Loading The type, form, and maximum quantity of special nuclear material per package are:
1.
3,510 grams U-235 provided the fuel is in the form of MTR-type fuel elements with each element containing no more than 351 grams U-235 and inserted in a spaced stainless steel fuel shipping basket described in GE Drawing No. 106D4150, Rev. O.
A shoring device to limit vertical motion of the fuel elements will be included.
The loading above qualifies as Fissile Class III under provisions of 10CFR71.40, and the maximum number of packages per shipment is one (1).
6.3 Model Specification The model for normal conditions is two casks side-by-side separated by 21.875 inches.
The 15-inch cask inside diameter and the 36.875-inch cask outside diameter provide this minimum separation radially.
When the overpacks are installed on each of the casks, the separation is greater; so the 21.875 inches is conservative.
The gap between the casks is filled with a water mist having a density of 8.8 E-5 grams H 0/ce, representing a humid condition of 2
saturated air et about 1200F and at atmospheric pressure.
The 8.8 E-5 density is then changed to 0.001, 0.01, 0.1, and 1.0 grams H 0/cc; and the k-effective values are calculated for each of these 2
densities.
These models are formed with the ten fuel elements loaded inside a basket for each cask, but the two baskets and the 21.875 inches separating them are formed outside of the cask.
This two-basket array is reflected on all sides by 12 inches of water.
2
The model for one cask under accident conditions involves ten fuel elements loaded in a basket that is fully flooded and reflected on all sides by 12 inches of water.
The model is formed outside the cask, even though the flooding inside the cask would give a lower k-effective due to less water reflection immediately around the basket, and due to the neutron poisoning of the steel forming the cask cavity inside the cask and supporting the lead outside the cask.
Therefore, the modeling of the fuel elements in the basket outside of the cask is conservative; and the same model may be used for determining k-effective values under conditions of underwater loading of the basket.
More details of this model are described below.
6.3.1 Description of Calculational Models In this calculation, each fuel plate in a fuel element and each fuel element in a basket are described in three dimensions discretely.
The model is prepared as input to the SCALE System using the 27GROUPNDF4 cross-section set and the KENO-IV criticality code to perform the k-effective calculations.
The fuel element modeling is described first.
Then the basket modeling is presented.
Each fuel element contains 20 plates:
18 fuel plates are in the middle of the fuel cleraent, and two aluminum plates are at the top and bottom of each fuel element, respectively.
Each fuel plate contains fuel meat that is 2.25 inches wide, 0.0228 inches thick, and 22.75 inches long.
Each fuel plate contains 19.5 grams U-235 in this fuel meat space.
The fuel meat is clad with 0.0136 inches of aluminum such that the fuel plate thickness becomes 0.05 inches.
3
a e
Each fuel plate in the fuel element is separated by a gap of 0.096 inches in the center of the fuel element.
These gap thicknesses change in the outer three layers to 0.108 inches, 0.118 inches, and 0.100 inches, respectively.
See Figure 6.3.1-1.
The aluminum beyond the 2.25-inch width and the 22.75-inch length of the fuel meat is represented as either water or water mist in this model.
The numerical results of this modeling may be seen in Table 6.3.1-1 under Box Type 1 or Box Type 2.
The basket is modeled as a 304 stainless steel structure that has walls which are 0.25 inches thick and contain ten holes that measure 3.18 inches square by 22.75 inches long.
There are three holes in the upper and lower rows and four holes in the middle row sufficient to hold 10 fuel elements.
See Figure 6.3.1-2.
The numerical results of this modeling may be seen in Table 6.3.1-1, and the arrangement of all the boxes showing two baskets separated by 21.875 inches may be seen in the same table in between the END GEOMETRY and END KENO cards.
6.3.2 Package Regional Densitg The number densities for the materials used in this model may be seen in Tables 6.3.1-1 and 6.4-1 through 6.4-5.
The number density used for the fuel meat was 0.00261362 atoms / barn-cm for U-235.
A molecular weight of 235.043933 gram /grara-mole and an Avogadro's number of 6.025 E23 gram-atom / gram-mole were used in calculating this number density.
Other materials in the fuel meat such as U-238, oxygen, silicone, etc., were not modeled.
The number densities for the materials specitled in Table 6.3.1-1 that are provided by the SCALE system for the 27GROUPNDF4 cross-section set are shown in Tables 6.4-1 through 6.4-5.
4 l
6.4 Criticality Calculations The SCALE
- Sy stem that is running on the Control Data Corporation 7600 Computer at General Electric's Nuclear Energy Business Operations was used for the k-effective calculations.
The 27GROUPNDF4 cross-section set and the KENO-IV criticality code in the SCALE system were used to perform these calculations.
The results of these calculations may be seen in Figure 6.4-1 and in Tables 6.4-1 through 6.4-5.
In Figure 6.4-1, k-effective values are plotted as a function of mist density.
These results show the peak k-effective to be less than 0.87 for the fully water-flooded accident condition, and less than 0.33 for the mist densities up to 0.1 grams H 0/cc.
Thirty-2 thousand neutron histories were run to obtain the 0.87 k-effective result.
However, all of the mist density calculations were stopped by a 15-minute time limit.
The smallest number of histories run was 25,500.
More detailed numerical results of all of these calculations may be seen in Tables 6.4-1 through 6.4-5.
6.5 C_ritical Benchmark Experiments In the discussion below, the benchmark experiments are presented first.
This is followed by tables showing models of these experiments prepared as input to the SCALE system.
Then the k-effective results using these models are presented, followed by the determination of biases required for each of the types of fissile material.
I
- Bucholz, J. A., " SCALE:
A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation", NUREG/CR-0200, j
ORNL/NUREG/CSD/2, Volume 1, Oak Ridge National Laboratory: July, 1980.
5
=
6.5.1 Benchmark Experiments and Applicability Uranium with enrichments varying from 1.3 w/o to fully enriched and plutonium are the fissile materials that are considered in the validation of SCALE for this evaluation.
The forms include fully enriched homogeneous uranium-water mixtures, low-enriched heterogeneous uranium dioxide-water mixtures, and homogeneous plutonium-water mixtures, in Table 6.5.1-1 below, critical experiments suitable for validation are identified.
6.5.2 Details of the Benchmark Calculations Models of TRX-1 and TRX-2 prepared as input to the SCALE
. system are shown in Tables 6.5.2-1 and 6.5.2-2, respectively.
Models of ORNL-1 and ORNL-2 are shown in Table 6.5.2-3.
Models of PNL-1 and PNL-2 are shown in Table 6.5.2-4.
Models of the B&W UO r d and MO r d are shown in Table 6.5.2-5.
2 2
6.5.3 K-Effective Results of the Benchmark Calculations K-effective results are presented for the ORNL, PNL, TRX, and BaW critical experiments in Table 6.5.3-1.
It is concluded that use of the SCALE System using the 27GROUPNDF4 cross-section set requires a negative 0.3 percent bias on the one sigma deviation for fully enriched uranium solutions and no bias for plutonium solutions; a negative bias of 2.3 percent on the mean value and 0.3 percent on the one sigma deviation for the multiplication factor must be applied for low-enriched, clumped uranium rods in water.
i A bias of 2.3 percent on the mean value and 0.3 percent on the one sigma deviation is applied to the k-effective results in Figure 6.4-1 in this evaluation.
6
FIGURE 6.3.1-1 FUEL ELEMENT SCHEMATIC
_.100
.118
.108
~
.096 a
Water Gaps, inches v
.096
.108
.118
.100 7
9 FIGURE 6.3.1-2 FUEL BASKET SCHEMATIC i
i l
1 1
l 1
I l
O o
s A'
1 hO f
(
n
'5 L
I l
l
}
}
l 5
lz d
t i
1 1
i t.
J
=
I 1
)
1 l
1 f
A g
y i
~
vs n~
n
- m -
i, g 9 ')
39 j. k..
a...
..q.-..
5.- -.L.
..g...
. a..-
O 8
y.
TABLE 6.3.1-1 KEFF BNL FUEL SHIPPING ARRAY FWR 2 CONT SIDE-BY-SIDE 27GROUPNDF4 7
7 3
LATTICECELL O
O U-235 1
O.
2.61362-3 END AL 2 1.
END H2O 3 8.8-5 END AL 4
1.
END H2O 5 1.
END SS304 6 1.
END H2O 7 8.8-5 END SYMMSLABCELL O.37084 0.057912 1 3 0.127 2 END KEFF BNL FUEL SHIPPING ARRAY FWR 2 CONT SIDE-BY-SIDE 15.0 103 300 3 16 21 51 O BOX TYPE 1
CUBOID 3
0.
-2.857500
.121920
.121920 28.892500 -28.892500 -0.5 CUBOID 2
O.
-2.857500
.156464
.156464 28.892500 -28.892500 -0.5 CUBOID 1
O.
-2.857500
.214376
.214376 28.892500 -28.892500 -0.5 CUBOID 2
O.
-2.857500
.248920
.248920 28.892500 -28.892500 -0.5 CUBOID 3
O.
-2.857500
.492760
.492760 28.892500 -28.892500 -0.5 CUBOID 2
O.
-2.857500
.527304
.527304 28.892500 -28.892500 -0.5 CUBOID 1
O.
-2.857500
.585216
.585216 28.892500 -28.892500 -0.5 CUBOID 2
O.
-2.857500
.619760
.619760 28.892500 -28.892500 -0.5 CUBOID 3
O.
-2.857500
.863600
.863600 28.892500 -28.892500 -0.5 CUBOID 2
O.
-2.857500
.898144
.898144 28.892500 -28.892500 -0.5 CUBOID 1
O.
-2.857500
.956056
.956056 28.892500 -28.892500 -0.5 CUBOID 2
O.
-2.857500
.990600
.990600 28.892500 -28.892500 -0.5 CUBOID 3
O.
-2.857500 1.234440 -1.234440 28.892500 -28.892500 -0.5 CUBOID 2
O.
-2.857500 1.268984 -1.268984 28.892500 -28.892500 -0.5 CUBOID 1
O.
-2.857500 1.326896 -1.326896 28.892500 -28.892500 -0.5 CUBOID 2
O.
-2.857500 1.361440 -1.361440 28.892500 -28.892500 -0.5 CUBOID 3
O.
-2.857500 1.605280 -1.605280 28.892500 -28.892500 -0.5 CUBOID 2
O.
-2.857500 1.639824 -1.639824 28.892500 -28.892500 -0.5 CULOID 1
O.
-2.857500 1.697736 -1.697736 28.892500 -28.892500 -0.5 CUBOID 2
O.
-2.857500 1.732200 -1.732280 28.892500 -28.892500 -0.5 CUBOID 3
O.
-2.857500 1.976120 -1.976120 28.892500 -28.892500 -0.5 CUBOID 2
O.
-2.857500 2.010664 -2.010664 28.892500 -28.892500 -0.5 CUBOID 1
O.
-2.857500 2.068576 -2.068576 28.892500 -28.892500 -0.5 CUBOID 2
O.
-2.857500 2.103120 -2.103120 28.892500 -28.892500 -0.5 CUBOID 3
O.
-2.857500 2.346960 -2.346960 28.892500 -28.892500 -0.5 CUBOID 2
O.
-2.857500 2.381504 -2.381504 28.892500 -28.892500 -0.5 CUBOID 1
O.
-2.857500 2.439416 -2.439416 28.892500 -28.892500 -0.5 CUBOID 2
O.
-2.857500 2.473960 -2.473960 28.892500 -28.892500 -0.5 CUBOID 3
0.
-2.857500 2.748280 -2.748280 28.892500 -28.892500 -0.5 CUBOID 2
O.
-2.857500 2.782824 -2.782824 28.892500 -28.892500 -0.5 CUBOID 1
O.
-2.857500 2.840736 -2.840736 28.892500 -28.892500 -0.5 CUBOID 2
O.
-2.857500 2.875280 -2.875280 28.892500 -28.892500 -0.5 CUBOID 3
O.
-2.857500 3.175000 -3.175000 28.892500 -28.892500 -0.5 CUBOID 2
O.
-2.857500 3.209544 -3.209544 28.892500 -28.892500 -0.5 CUBOID 1
O.
-2.857500 3.267456 -3.267456 28.892500 -28.892500 -0.5 CUBOID 2
O.
-2.857500 3.302000 -3.302000 28.892500 -28.892500 -0.5 CUBOID 3
O.
-2.857500 3.556000 -3.556000 28.892500 -28.892500 -0.5 CUBOID 2
O.
-2.857500 3.683000 -3.683000 28.892500 -28.892500 -0.5 CUBOID 7
0.000
-4.039 4.039
-4.039 28.8925
-28.8925 -0.5 CUBOID 6
0.000
-4.356 4.356
-4.356 28.8925
-28.8925 -0.5 9
o TABLE 6.3.1-1 (CONTINUED) j BOX TYPE 2
CUBOID 3
2.857500
-0.
.121920
.121920 28.892500 -28.892500 -0.5 CUBOID 2
2.857500
-0.
.156464
.156464 28.892500 -28.892500 -0.5
)
CUBOID 1
2.857500
-0.
.214376
.214376 28.892500 -28.892500 -0.5 CUBOID 2
2.857500 -0.
.248920
.248920 28.892500 -28.892500 -0.5 CUBOID 3
2.857500
-0.
.492760
.492760 28.892500 -28.892500 -0.5 CUBOID 2
2.857500
-0.
.527304
.527304 28.892500 -28.892500 -0.5 CUBOID 1
2.857500 -0.
.585216
.585216 28.892500 -28.892500 -0.5 CUBOID 2
2.857500
-0.
.619760
.619760 28.892500 -28.892500 -0.5 CUBOID 3
2.857500
-0.
.863600
.863600 28.892500 -28.892500 -0.5 CUBOID 2
2.857500
-0.
.898144
.898144 28.892500 -28.892500 -0.5 CUBOID 1
2.857500
-0.
.956056
.956056 28.892500 -28.892500 -0.5 CUBOID 2
2.857500 -0.
.990600
.990600 28.892500 -28.892500 -0.5 CUBOID 3
2.857500 -0.
1.234440 -1.234440 28.892500 -28.892500 -0.5 CUBOID 2
2.857500 -0.
1.268984 -1.268984 28.892500 -28.892500 -0.5 CUBOID 1
2.857500
-0.
1.326896 -1.326896 28.892500 -28.892500 -0.5 CUBOID 2
2.857500 -0.
1.361440 -1.361440 28.892500 -28.892500 -0.5 CUBOID 3
2.857500
-0.
1.605280 -1.605280 28.892500 -28.892500 -0.5 CUBOID 2
2.857500 -0.
1.639824 -1.639824 28.892500 -28.892500 -0.5 CUBOID 1
2.857500
-0.
1.697736 -1.697736 28.892500 -28.892500 -0.5 CUBOID 2
2.857500
-0.
1.732280 -1.732280 28.892500 -28.892500 -0.5 CUBOID 3
2.857500
-0.
1.976120 -1.976120 28.892500 -28.892500 -0.5 CUBOID 2
2.857500
-0.
2.010664 -2.010664 28.892500 -28.8925u0 -0.5 CUBOID 1
2.857500
-0.
2.068576 -2.068576 28.892500 -28.892500 -0.5 CUBOID 2
2.857500
-0.
2.103120 -2.103120 28.892500 -28.892500 -0.5 CUBOID 3
2.857500 -0.
- 2. 346960 -2. 346960 28. 892500 -28. 8925C O -0. 5 CUBOID 2
2.857500
-0.
2.381504 -2.381504 28.892500 -28.892590 -0.5 CUBOID 1
2.857500
-0.
2.439416 -2.439416 28.892500 -28.892500 -0.5 CUBOID 2
2.857500
-0.
2.473960 -2.473960 28.892500 -28.892500 -0.5 CUBOID 3
2.857500
-0.
2.748280 -2.748280 29.892500 -28.892500 -0.5 CUBOID 2
2.857500
-O, 2.782824 -2.782824 28.892500 -28.892500 -0.5 CUBOID 1
2.857500
-0.
2.040736 -2.840736 28.892500 -28.892500 -0.5 CUBOID 2
2.857500
-0.
2.875280 -2.875280 28.892500 -28.892500 -0.5 CUBOID 3
2.857500
-0.
3.175000 -3.175000 28.892500 -28.892500 -0.5 CU2OID 2
2.857500 -0.
3.209544 -3.209544 28.892500 -28.892500 -0.5 CUBOID 1
2.857500 -0.
3.267456 -3.267456 28.892500 -28.892500 -0.5 CU!OID 2
2.857500 -0.
3.302000 -3.302000 28.892500 -28.892500 -0.5 CUBOID 3
2.857500
-0.
3.556000 -3.556000 28.892500 -28.892500 -0.5 CUBOID 2
2.857500
-0.
3.683000 -3.683000 28.892500 -28.892500 -0.5 CUBOID 7
- .039
-0.000 4.039
-4.039 28.8925
-28.8925 -0.5 CUBOID 6
s.
56
-0.000 4.356
-4.356 28.8925
-28.8925 -0.5 BOX TYPE 3
CUBOID 7
4.039
-0.000 4.356
-4.039 28.8925
-28.8925 -0.5 CUBOID 6
4.356
-0.000 4.356
-4.356 28.8925
-28.8925 -0.5 BOX TYPE 4
CUBOID 7
4.039
-0.000 4.039
-4.356 28.8925
-28.8925 -0.5 CUBOID 6
4.356
-0.000 4.356
-4.356 28.8925
-28.8925 -0.5 COX TYPE 5
CUBOID 7
0.000
-4.039 4.039
-4.356 28.8925
-28.8925 -0.5 CUBOID 6
0.000
-4.356 4.356
-4.356 28.8925
-28.8925 -0.5 BOX TYPE 6
CUBOID 7
0.000
-4.039 4.356
-4.039 28.8925
-28.8925 -0.5 CUBOID 6
0.000
-4.356 4.356
-4.356 28.8925
-28.8925 -0.5 10
TABLE 6.3.1-1 (CONTINUED)
COX TYPE 7
CUBOID 6
0.000
-4.356 0.317
-0.000 28.8925
-28.8925 -0.5 BOX TYPE 8
CUBOID 6
0.000
-0.317 4.356
-4.356 28.8925
-28.8925 -0.5 BOX TYPE 9
CUBOID 7
4.039
-0.000 0.317
-0.000 28.8925
-28.8925 -0.5 CUBOID 6
4.356
-0.000 0.317
-0.000 28.8925
-28.8925 -0.5 BOX TYPE 10 CUBOID 7
0.000
-4.039 0.317
-0.000 28.8925
-28.8925 -0.5 CUBOID 6
0.000
-4.356 0.317
-0.000 28.8925
-28.8925 -0.5 BOX TYPE 11 CUBOID 7
0.000
-0.317 4.356
-4.039 28.8925
-28.8925 -0.5 CUBOID 6
0.000
-0.317 4.356
-4.356 28.8925
-28.8925 -0.5 BOX TYPE 12 CUBOID 7
0.000
-0.317 4.039
-4.356 28.8925
-28.8925 -0.5 CUBOID 6
0.000
-0.317 4.356
-4.356 28.8925
-28.8925 -0.5 BOX TYPE 13 CUBOID 7
0.317
-0.000 0.317
-0.000 28.8925
-28.8925 -0.5 COX TYPE 14 CUBOID 7 27.78125
-27.78125 0.317
-0.000 28.8925
-28.8925 -0.5 COX TYPE 15 CUBOID 7 27.781.'5
-27.78125 4.356
-4.356 28.8925
-28.8925 -0.5 BOX TYPE 16 CUBOID 7 27.70125
-27.78125 4.356
-4.356 28.8925
-28.8925 -0.5 ARRAY BDY 7 63.26325 -63.26325 13.385
-13.385 28.8925 -28.8925 -0.5 CUBOID 5
93.74325 -93.74325 43.865
-43.865 59.37250
-59.37250 -0.5 END GEOMETRY O 13 9
7 7
7 7
7 7 10 13 14 13 9
7 7
7 7
7 7 10 ~3 11 3
1 2
1 2
1 2
6 11 15 11 3
1 2
1 2
1 2
6 11 8
1 2
1 2
1 2
1 2
8 16 8
1 2
1 2
1 2
1 2
8 12 4
1 2
1 2
1 2
5 12 15 12 4
1 2
1 2
1 2
5 12 13 9
7 7
7 7
7 7 10 13 14 13 9
7 7
7 7
7 7 10 13 0
END KENO 11
1 TABLE 6.4-1 rEFF BNL FUEL SHIPPIN5 ARPAf FNR 2 CONT SICE-BY-SIDE 276R00PCF4 7 7 3 1ATTICECELL 0 0-U-235 1 0. 2.61362-3 END AL 21. EE
^
H2O 3 6.8-5 END AL 4 1. END H2O 5 1.' END 55304 6 1. EhD H2O 7 B.B-5 END SYMM9LABCELL 0.37084 0.057912 1 3 0.127 2 END M!!TURE huCLIDE DENSITY MIITUEE N'jCLIDE DENSITV 1
-92235 2.61362E-03 8
-92235 4.06154E-04 2
13027 6.02!S3E-02 6
13027 1.12225E-02 3
1001 5.6744BE 0 1001 3.862e7E-06 3
8016 2.93724E-06 8
B016 1.93134E-06 4
3 6.02383E-02 5
5 6.67555E-02 5
8 3.23777E-02 6
24304 1.74239E-02 6
25055 1.73634E-03 6
26304 5.93316E-02 6
26304 7.72036E-03 7
6 ' 5.8744BE-06 7
9 2.93724E-06 CROSS SECTION! READ FROM TAPE NUCLICE =
1001 H 1169 F, 1002 i 210 GF 032475i2)
NUCLIDE =
5 H 1269 F, 1002 T 218 GP 032475(2)
NUCLIDE =
6 H 1269 F, 1002 T 218 BP 032475(2)
NUCLICE =
8016 0-16 1276 21E SP 030476(7)
NUCLIDE =
8 0-16 1276 218 6P 030476(7)
NUCLIDE =
9 0-16 1276 218 6P 030476(7)
NUCLIDE=
13027 AL-27 1193 218 6P 040375(5)
NUCLIDE =
3 AL-27 1193 218 6P 040375(5)
- NUCLIDE =
24304 CR 1191 NT SS-304(1/EST) P-3 293K SF=5+4(423751' NUCLIDE =
25055 MN-55 1197 S!68=5+4 NENILACS 21BN6D F-3 293K NUCLIDE =
26304 FE 1192 NT SS-304(1/EST) P-3 293K SF=5+4(42375)'
NUCLIDE =
28304 NI 1190 NT SS-304(1/EST) F-3 293K SP=5+4(423751' NUCLIDE =
92235 U-235 1261 S16P=5+4 NENILACS 21BNBP F-3 293Kt3)
SENERA'!ONS AVERAGE 67 PER CENT 95 PER CENT 99 FER CENT NU'IEL CT SKIPPED K-EFFECTIVE DEVIATION CONFIDENCE INTERVAL CON:!DENCE INTERVAL CONC!DENCE INTERVAL h!STCE1EE 3
.26772 + OR -.00301
.26470 TO.27073
.26te9 TO.27374
.25868 TO.27676 2550)
FREQUENCY FOR SENERATIONS 4 TO BB
.1869 TO.2100 e
.2100 TO.2331
.2331 TO.2562 setenneeeeenenneeen
.2562 TO.2793 auseuennununenuneen
.2793 TO.3024 e n n eeu u n n u n
.3024 TO.3255 en
.3255 TO.3485 seen 12
TABLE 6.4-2 KEFF BNL FUEL SHIPP1NS ARRAY FWR 2 CCNT SIDE 4Y-SIDE 276FDUPNLF4 7 7 3 LATTICECELL 0 0 U-235 1 0. 2.61362-3 END AL 2 1. END H2O 3 1.-3 END AL 4 1. END H2O 5 1. ENL SSX4 6 1. EhD H2O 7 1.-3 END STFMSLA3 CELL 0.37084 0.057912 1 3 0.127 2 END MIITUFE NU: LICE DENSITY M11TLIE NUCLIDE DENSIT) 1
-92135 2.61!62E-03 8
-92235 4.0B158E-04 2
13027 6.02383E-02 8
13027 1.12225E-02 3
1001 6.67555E-05 B
1001 4.38940E-05 3
8016 3.33777E-05 8
8016 2.19470E-05 4
3 6.02383E-02 5
5 6.67555E-02 5
8 3.33777E-02 6
24W4 1.74239E-02 6
250'5 1.7363E-0?
6 26304 5.D3526E4?
6 28M4 7.7203t!-03 7
6 6.67555E-05 7
9 3.33777E-05 CRCSS SEti10NE READ FROM 7 APE ~
NUCLlDE =
1001 H 1269 F, 1002 T 218 6P 032475(2)
NUCL1DE =
5 H 1269 F, 100' T 218 SP 032475(2)
NUCL10E =
6 H 1269 F, 1002 1 218 6P O!2475(2) huCL10E =
6016 0-16 1276 218 GP 030476(7)
~NUCLICE =
8 0-16 1276 218 GP 030476(7)
NUCLIDE =
9 0-16 1276 215 GP 030476(7)
NUCLIDE =
13027 AL-27 1193 218 SP 040375(5)
WUCLIDE =
3 AL-27 1193 218 6P 040375(5)
NUCLIDE =
24304 CR 1191 WT SS-304(1/EST) P-3 293K SF=5+4(423751' NUCLIDE =
25055 MN-55 1197 S16P=5+4 NEWILACS 21GN6P P-3 29%
NUCLICE =
26304 FE 1192 WT SS-304(1/EST) P-3 293K SP=5+4(42!75)*
NUCLIDE =
28304 N1 1190 WT SS-304(1/EST) P-3 293K SP=5+4(42375;'
NUCLIDE =
92235 U-235 1261 S16P=5+4 NEWILACS 21BN6P P-3 293K(3)
SENERATIONS AVERA6E 67 PER CENT 95 FER CENT 99 FER CENT Nur.EEF 0F SKIPPED K-EFFECTIVE DEVIATION CONFIDENCE INTERVAL CONFIDENCE INTERVAL CONFIDENCE INTEFVAL HIS70^ ES 3
.27187 + OR -.00299
.26888 TO.27496
.26589 TO.27786
.26290 TO.26085 25500 FRE90ENCY FOR SENERATIONS 4 TO 88
.1679 TO.1910
.1910 TO.2141
.2141 TO.2372
- H
.2372 TO.2603 HeeeHeeHHHe
.2603 TO.2834 H H oH tH 4H 64t H Ht H t4H H
.2834 TO.3065 HHHHeHeHHHHH
.3065 TO.3296 HHH
.3296 TO.3527 13
4 0 '.
TABLE 6.4-3
.KEFF BNL FUEL SHIPPING AFRAY FWR 2 CONT SIDE 4Y-S!DE 276RDuPNIF4 7 7 3 LATTICECELL 0- 0 U-235 1 0, 2.613 0-3 ENL AL 2 1. END H2O 31.-2 EN:-
- A1. 4 1. END
. H2O -5 1. END ES304 6 1. END H2O 7 1.-2 EN3
!VMMSU3 CELL 0.37084 0.0579'I 1 3 0.127 2 END MllTURE NJCLIDE uEhSITY MIITURE NJCLIEE CENSITY
-1
-922% 2.61362E-03 6
-92235 4.0615sE-04 2
13027 6.02383E-02 8
13027 1.12225E-02 3
1001 6.67555E-04 8
1001 4.3B940E-04
'3 8016 3.33777E-04 8
8016 2.19470E-04 4
3 6.02383E-02 5
5 6.67555E-02 5
8 3.33777E-02 6
24304 1.74239E-02 6
25055 1.73634E-03 6
26304 5.93526E-02 6
28304 7.72036E-03 7
6 6.67555E-04 7
9 3.33777E-04 CRDSS SECTIONS READ FROM TAPE NUCLIDE =
1001.H 1269 F, 1002 1 218 6P 032475(2)
NUtiltE =
5 H 1269 F, 1002 T 218 69 032475(2)
NU:LIDE =
6 H 1269 F, 1002 T 218 6P 032475(2)
NUCLIDE =
8016 0-16 1272 218 6P 030476(7)
NUCLIDE =
8 0-16 1276 218 65 030476(7)
NUCLIDE =
9 0-16 1276 218 SP 030476(7)
NUCLIDE=
13027 AL-27 1193 218 6P 040375(5)
NJCLIDE =
3 AL-27 1193 218 6P 040375(5)
WU2LIDE =
24304 CR 1191 NT SS-304(1/EST) P-3 293K EP=5+4(423751' NUCL10E =
25055 MN-55 1197 516P=5+4 NENILACS 21BN6F F-3 293h NUCLICE =
26304 FE !!92 NT SS-304(1/EST) P-3 293K SP=5+4(42375U NUCLIDE =
28304 NI 1190 NT SS-30411/EST) P-3 293K Sp=5+4(42375)*
NUCLIDE =
92235 U-2351261 S16P=5+4 NENILACS 218h3P P-3 293(C)
BENERATIONS AVERASE 67 PER CENT 95 FER CENT 99 fen CENT N'JMPEE 0F SKIPPED K-EFFECTIVE DEVIAi!DN C0F IDENCE INTERVAL COWIDENCE INTERVAL CONFIDENCE INTERVAL HISIGFIES 3-
.26963 + OR -.00313
.26650 TO.27275
.26339 TO.27589
.26025 TO.27900 25500 FREQUENCY FOR GENERATIONS 4 TD 88
.1888 TO.2119-ee
.2119 TO.2350 eusene
.2350 TD.2581 sennuneenen
.2581 TO.2812
- eseee n nee neen n en eeees
.2812 TO.3043 -
usesseeesenen
.3043 10.3274 noneen
.3274 TO.3505 14
TABLE 6.4-4 KEFF BNL Fl!EL SHIPPING ARRAY FNR 2 CONT SIDE-BY-S!DE 276ROUPNtF4 7 7 3 LATTICECELL 0 0 U-235 1 0. 2.61362-3 END AL 2 1. EN2 H2O 3 1.-1 END AL 4 1. END H2D 5 1. EkD 55304 6 1. Eht H23 7 1.-1 Ekt SYMMSLAECELL 0.37064 C.05791213 0.127 2 END M!!TURE NUCLICE DENSITV RIITURE hUCLICE DENSITY 1
-92235 2.61362E-03 0
-92235 4.08154E-04 2
13027 6.02383E-02 8
13027 1.12225E-02
.3
-1001 6.67555E-03 8
1001 4.38940E-03 3
8016 3.33777E-03 0
8016 2.19470E-03 4
3 6.02M3E-02 5
5 6.67555E-02 5
8 3.33777E-02 6
24304 1.74239E-02 6
25055 1.73634E-03 6
26304 5.93526E-02 6-2E304 7.720!6E-03 7
6 6.67555E-03 7
9 3.33777E-0!
CPOSS SECTIONS READ FP09 TA?E NLCLICE =
1001 H 1269 F, 1002 1 218 6P 032475(2)
N' CL12E =
5 H 1269 F, 1002 T 219 63 032475t21 J
WJC1.!LE =
6 H 1269 F, 1002 i 210 SP 032475(2)
NUCL10E =
0016 0-16 1276 218 SP 030476(7)
N'JCLlDE =
2 0-16 1276 219 6P 030476(7)
NUCLILE =
9 0-16 1276 216 60 030476(7)
NUCLIDE =
13027 AL-271193 218 6P 040375(5)
NbCLICE =
3 AL-27 1193 218 6P 040375(5)
NUCLIOE =
24304 CR !!91 di SS-304(1/EST) P-3 293K SP=5+4(42375)'
NUCLIDE =
25055 MN-55 1197 SIEP=5+4 NEWILA2S 21BNBP P-3 29k NUCL!DE =
26304 FE 1192 NT SS-304(1/EST) P-3 293K SF=5+4(423751' NUCLICE =
29304 N1 !!90 el SS-304(1/EST) P-3 293K SP=5+4(423751' WUCLIDE =
92235 U-235 1261 $16745+4 NEW1LACS 210NSF F-3 293r(3)
SENERAi!ONS AVEFASE 67 FER CENT 95 PER CENT 99 FER Cfhi n'JiEF 0; SKIPPED K-EFFECTIVE LEVIATION CONFIDENCE INTEP#L CONFl ENCE INTERVAL CONFICEhCE INTERVAL HISTORIES 3
.29635 + OR -.00309
.29326 TO.29944
.29017 TO.30252
.28706 TO.30561 264M FREQUENCY FOR GEhERATIONS 4 TO 91
.2386 10.2617 enenense
. 2617 10.2648 eseeeHeeeHHeeeeeeH
.2840 10.3079 ausentenuesessenne
.3079 TO.3310 ennuunseeeeeenu
.3310 10.3541 eeenes
.3541 10.3772 15 l
~,
TABLE 6.4-5 KEFF BNL FUEL SHIFPING ARRAY FNR 276R00FNDF4 7 7 3 LATilCECELL 0 0 U-235 1 0. 2.61362-3 END AL 2 1. END H2O 3 1. END AL 4 1. END H2O 5 1. END SS304 6 1. END H2O 7 1. END SYMM!LABCELL 0.37084 0.057912 1 3 0.127 2 END M11TURE NUCLIDE DENSITY MllTURE NUCLIDE DENSITY 1
-92235 2.61362E-03 8
-92235 4.08154E-04 2
13027 6.02383E-02 8
13027 1.1222:E-02 3
1001 6.67555E-02 8
1001 4.38940E-02 3
8016 3.33777E-02 8
8016 2.19470E-02 4
3 6.02383E-02 5
5 6.67555E-02 5
8 3.33777E-02 6
24304 1.74239E-02 6
25055 1.73634E-03 6
26304 5.93526E-02 6
28304 7.72036E-03 7
6 6.6755!E-C2 7
9 3.33777E-02 CROSS SECTIONS READ FROM TA'E NUCL!DE =
1001 H 1269 F, 1002 T 218 SP 032475(2)
NUCLIDE =
5 H 1269 F, 1002 T 218 BP 032475(2)
NUCLIDE =
6 H 1269 F, 1002 T 218 6P 032475(2)
NUCL!DE =
6016 0-16 1276 218 EP 030476(7)
NUCLIDE =
8 0-16 1276 218 EP 030476(7)
NUCLIDE =
9 0-161276 218 GP 030476(7)
NUCLlDE =
13027 AL-27 1193 218 BP 040375("O NUCLIDE =
3 AL-27 1193 218 6P 040375(5)
NUCLIDE =
24304 CR 1191 NT SS-304(1/EST) P-3 293K SP=5+4(42375)'
NUCL!DE =
25055 MN-55 1197 S!6P=5+4 NENILACS 218N6F P-3 293t NUCLIDE =
26304 FE 1192 NT SS-304(1/EST) P-3 293K SP=5+4(42375)'
NUCLIDE =
28304 N1 1190 NT SS-304(1/EST) P-3 293K SP=5+4(423751' NUCLlDE =
92235 U-235 1261 S16P=5+4 NENILACS 21BNBP P-3 293K(3)
SENERATIONS AVERASE 67 FER CENT 95 FER CENT 99 FER CENT N #iES DT SKIPPED K-EFFECTIVE DEV!ATICN CONFIDENCE INTERVAL CONFIDEN:E INTERVAL CONFIDEkCE 14TERVA'. HISTC51ES 3
.81978 + OR -.00475
.81502 TO.82453
.81027 TO.82929
.80551 TO.83404 300M FREQUENCY FOR GENERATIONS 4 TO 103
.6928 TO.7159 ee
.7159 TO.7369 neun
.7389 TO.7620 He
.7620 TO.7851
- eet
.7851 TO.8082 ennuunu
.8082 TO.8313 nunnunnunn
.8313 10.8544 eennuseenennu
.8544 TO.8775 ennununne
.8775 TO.9006 neeen
.9006 10.9237
.9237 TO.9468 e
16
FIGURE 6.4-1: K-Effcctiva (12 Sigmn) Vs. Wst=r Mist Drnsity For Modal 2.
Two Cczko, Ecch Contcining 3510 Grtms U-235 Of Fully Enriched Uranium In Plate Fuel In Ten Fuel Elements In A 304 Stainless Steel Basket, Are In An Array Separated By 21.875" Edge-To-Edge Containing A Mist.
There Is 12" Of Water Reflection Around The Array. The K-Effective Results Contain A Bias Of 0.3% In The 1 Sigma Value And 2.3% In The Mean Value.
1.O----------*----
l l
l l
l l
l l
l l
l i
i i
K I
i l
l l
l E
I i
i F
l I
F i
l l
l l
J E
O.8-----
=-
C T
l l
l l
l l
l I
i i
i V
E i
i i
I i
i l
l l
l O.6--------------------
=----------- ---
l l
l l
l l
l l
l l
1 i
i i
i i
i i
i i
i i
i l
l t
i O.4---------
l 1
I i
l l
l l
1 i
1 1
i i
i s
i
.i i
i i
i i
O. 2-i i
i l
l l
l l
l l
l l
l l
l 1
i I
l l
l l
l l
l l
l i
i 1
i I
i I
O.
- ---------~~~---------~~~=
- - - - = = - - - - - - - - - - -
1.E-6 1.E-5 1.E-4 1.E-3 1.E-2 1.E-1 1.
MIST DENSITY, GRAMS WATER VAPOR /CC AIR 17
TABLE 6.5.1-1 Critical Experiments for Computational Tool Evaluation Experiment Name References A.
TRX-1 & TRX-2 A. I.
J. Hardy, Jr., D. Klein and Low-Enriched Uranium Rods J. J. Volpe; "A Study of Physics in Water Parameters In Several Water-Moderated Lattices of Slightly Enriched and Natural Uranium",
WAPD-TM-931; March,1970.
A.2.
J. Hardy, Jr., D. Klein and J. J. Volpe; Nucl. Sci. Eng.
40, 101 (1970).
J. J. Volpe, T Hardy, Jr., and D. Klein, Nucl. Sci. Eng. 40, 116 (1970).
A.3.
J. Hardy, Jr., D. Klein and R. Dannels; Nucl. Sci. Eng. 26, 462 (1966).
A.4.
J. R. Brown et al., " Kinetics and Buckling Measurements In Lattices of Slightly Enriched U or UO 2 Rods In H 0", WAPD-176 (January, 21958).
A.S.
R. Sher and S. Fiarman, " Studies of Thermal Reactor Benchmark Data Interpretation:
Experi-mental Corrections", EPRI NP-209; October, 1976.
B.
R. Gwin and D. W. Magnuson, Fully Enriched Uranium
" Eta of U-233 and U-235 for Spherical Solutions Critical Experiments", Nuc. Sci.
Eng.12, 364 (1962).
B.2.
A. Staub et al., " Analysis of A Set of CWical Homogeneous U-H O Spheres", Nuc. Sci. Eng.
34, 2263 (1968).
1 18
TABLE 6.5.1-1 (Continued)
Experiment Name References C.
PNL 1-5 C.1.
R. C. Lloyd et al., " Criticality Plutonium Spherical Solutions Studies With Plutonium Solutions",
Nuc. Sci. Eng. 25, 165 (1966).
C.2.
L. E. Hansen and E. D. Clayton,
" Theory-Experiment Tests Using ENDF/B Version 11 Cross-Section Data", Trans. Amer. Nuc. Soc.
5, 309 (June,1972).
C.3.
F. E. Kruesi et al., " Critical Mass Studies of Plutonium-Nitrate i
Solution", HW-24514 (1952).
D.
Babcock & Wilcox D.1.
M. N. Baldwin et al., " Physics Small Lattice Facility Verification Program - Part III",
Low-Enriched UO Rods BAW-3647-6, Babcock & Wilcox, 2
in Water 1970.
MO Rods in Water D.2.
G. T. Fairburn et al., "Pu Lattice 2
Experiments In Uniform Test Lattice of UO -1.5% PuO, Fuel",
BAW-1357, Ba, cock & Wilc5x; n
August, 1970.
19
l TABLE 6.5.2-1 TRX-1 BEFF TRX-1763 U IETE 80851291W/0 UAPD 176 JAN.1958 4
27B OUP S F4 7 10 4 LATTICECELL 0 0 F 235 1 0. 6.253-4 END F 238 1 0. 0.047205 EE i
E 2 0. 0.06025 END i
N 3 0. 0.06676 E M 0 3 0.' O.03333 E M 100 4 8.0-5 Em N 5 0. 0.06674 EE O 5 0. 0.03333 EE FE & 1. END E 7 0. 0.06025 EO TRIAP6 PITCH 1.806 0.983 1 3 1.1506 2 1.0004 4 EW IEFF TRX-1763 U lETAL SODS 1.291W/0 WAPD 176 JAN.1958 15.0 103 300 3 6 60 33 2 0 SDX TYPE 1 ZIEMICYL+X 7 0.5753 0. -15.24 -0.5 CWOID 5 0 903 -0. 0.782 -0.782 0. -15.24 4.5 CWOID 500 0.903 -0. 0.782 -0.782 0. -76.20 -0.5 CWOID & 0.903 -0. 0.782 4.782 5.03 -76.20 -0.5 EX TYPE 2 ZIEMICYL-X 7 0.5753 0. -15.24 4.5 CWOID 5 0. -0.903 0.782 -0.782 0. -15.24 -0.5 CWOID 500 0. -0.903 0.782 -0.782 0. -76.20 4.5 Ol801D 6 0. -0.M3 0.782 -0.782 5.03 -76.20 4.5 30X TYPE 3 IIEMICYL4X 7 0.5753 20.32 -0. 4.5 CWOID 5 0.M3 -0. 0.782 4.782 20.32 -0. -0.5 CUIDID 500 0.903 -0. 0.752 4.742 31.28 -0. -0.5 D20!D 6 0.M3 4. 0.782 -0.782 81.28 -1.27 -0.5 30X TYPE 4 2DEMICYL-X 7 0.5753 20.32 -0. -0.5 Cut 0!D 5 0. -0.M3 0.782 4.782 20.32 -0. -0.5 CWCID 500 0. -0.M3 0.782 -0.782 0128 -0. -0.5 CWOID 4 0. -0.903 0.782 4.782 81.28 -127 4.5 30X TYPE 5 CWOID 5 0.M3 -0. 0.782 -0.792 0. -76.20 4.5 CWOID 6 0.M3 -0. 0.782 4.782 5.M -76.20 4.5 30X TYPE 6 0201D 5 0.M3 4. 0.782 4.782 8128 -0. -0.5 CWOID 6 0.M3 -0. 0.782 4.782 0128 -1.27 4.5 AttAY sty 5 27.M 0 -27.090 25.006 -25.006 31.915 -81.915 -0.5 CWOID 5 57.090 -57.0M 55.006 -55.006 31.915 -81.915 4.5 l
l 20
TABLE 6.5.2-1 TRX-1 (CONTIIRED)
IEEFF TRX-1763 U ETAL RODS 1.291W/0 WAPD 176 JAN.1958 EIS EDETRY 5 1 60 1 1 33 1 2 2 1 0 6 1 60 1 13311110224382 13322210 1 25 39 2 1 33 2 2 2 1 0 2 17 43 2 2 32 2 2 2 1 0 1 18 44 2 2 32 2 2 2 1 0 214462 33122210115472 33122210213472 43022210 1 14 48 2 4 30 2 2 2 1 0 2 12 48 2 5 29 2 2 2 1 0 1 13 49 2 5 29 2 2 2 1 0 2 9 51 2 6 28 2 2 2 1 0 1 10 52 2 6 28 2 2 2 1 0 2 8 52 2 7 27 2 2 2 1 0 1 9 53 2 7 27 2 2 2 1 0 2 7 53 2 8 26 2 2 2 1 0 1 8 54 2 8 26 2 2 2 1 0 2 6 54 2 9 25 2 2 2 1 0 1 7 55 2 9 25 2 2 2 1 0 2 5 55 2 10 24 2 2 2 1 0 1 65621024222102 45421123222101 5572112322210 2 3 57 2 12 22 2 2 2 1 0 1 4 58 2 12 22 2 2 2 1 0 2 2 58 2 13 21 2 2 2 1 0 1 35921321222102 15921618222101 2602161822210 4 24 38 2 1 33 2 1 1 1 0 3 25 39 2 1 33 2 1 1 1 0 4 17 43 2 2 32 2 1 1 1 0 3 18 44 2 2 32 2 1 1 1 0 4 14 46 2 3 31 2 1 1 1 0 3 15 47 2 3 31 2 1 1 1 0 4 13 47 2 4 30 2 1 1 1 0 3 14 48 2 4 30 2 1 1 1 0 4 12 48 2 5 29 2 1 1 1 0 3 13 49 2 5 29 2 1 1 1 0 4 9 51 2 6 28 2 1 1 1 0 3 10 52 2 6 28 2 1 1 1 0
- . 8522 727211103 9532 727211104 7532 82621110 3 8542 826211104 6542 925211103 7552 92521110 4 5 55 2 10 24 2 1 1 1 0 3 4 56 2 10 24 2 1 1 1 0 4 4 56 2 11 23 2 1 1 1 0 3 5 57 2 11 23 2 1 1 1 0 4 3 57 2 12 22 2 1 1 1 0 3 4 58 2 12 22 2 1 1 1 0 4 2 58 2 13 21 2 1 1 1 0 3 3 59 2 13 21 2 1 1 1 0 4 1592161821110 3 2 60 2 16 18 2 1 1 1 9 END KENO 8
21
TABLE 6.5.2-2 TRX-2 EEFF TRX*2 577 U ET E RODS 1.291W/0 UAPD 176 JAN. 1958 27WOUPGF4 7 10 4 LATTICECELL 0 0 IF235 10. 6.253-4 ES U-230 1 0. 0.047205 E W K 2 0. 0.06025 END N 3 0. 0.06676 E W 0 3 0. 0.03330 Em N20 4 8.O-5 E E N 5 0. 0.06676 E W O 5 0. 0.03338 E W FE 6 1. END l
E 7 0. 0.06025 END
'1R14NOPITCH 2 174 0.983 1 3 1.1506 2 1.0004 4 END REFF TRX-2 577 U ETE ROBS 1.291W/0 MAPD 176 JAN.1958 I
15.0103 300 3 6 52 N 2 0 IOX TYPE 1 l'
M MICYL+X 7 0.5753 0. -15.24 -0.5 CWOID 5 1007 4. 0.941 -0.9410. -15.24 -0.5 01B01D 5001.M7 -0. 0.941 -0.9410. -76.20 -0.5 CWO!D 41.M7 -0. 0.941 -0.9415.08 -76.20 -0.5 30X TYPE 2 M MICYL-X 7 0.5753 0. -15.24 -0.5 CWOID 5 0. -1.007 0.941 -0.9410. -15.24 -0.5 CUB 0ID 500 C. -1.007 0.941 -0.941 0. -76.20 -0.5 CUB 0ID 6 0. -1.M7 0.9414.9415,08 -76.20 -0.5 30X TYPF. 3 s
M MICYLfX 7 0.5753 20.32 4. -0.5 CUB 0ID 5 1.097 -0. 0.941 -0.94120.32 4. -0.5 CWOID 5001.007 -0. 0.9414.94161.28 -0 4.5 CWo!D 61.007 4. 0.9414.94101.28 -1.27 -0.5 E X TYPE 4
M MICYL-X 7 0.5753 20.32 -0. 4.5 CWOID 5 0. -1.007 0.9414.94120'.32 4. 4.5 CUBOID 500 0. -1.M7 0.9414.94181.28 -0. -0.5 CUBOID 4 0. -1.M7 0.9414.94131.28 -1.27 -0.5 30X TYPE 5 CWOID 51087 -0. 0.9414.9410. -76.20 -0.5 CWOID & 1.087 4. 0.9414.9415.08 -76.20 4 5 30X TYPE 6 CWOID 51.087 -0. 0.941 -0.94131.20 -0. 4.5 CUB 0ID & 1007 4. 0.941 -0.94181.20 -1.27 -0.5 ARRAY 3DY 5 20.262 -28.262 27.289 -27.239 81.915 -0).915 -0.5 CWOID 5 50.262 -50.262 57.209 -57.299 81915 -81.915 -0.5 EB EDETRY e
51M1 1 N 12 210 6 1 M 1 1 N 11110 2 D R 2 1 N 2 2 210 1 23 33 2 1 29 2 2 2 1 0 2 15 37 2 2 28 2 2 2 1 0 1 16 30 2 2 28 2 2 2 1 0 212402 32722210113412 32722210211412 42622210 112422 42622210210422 52522210111432 52522210 l
2 7 4 2 6 24 2 2 2101 8 4 2 6 24 2 2 210 2 4 4 2 7 D 2 2 210 l
1 7 47 2 7 N 2 2 210 2 5 0 2 0 D 2 2 2101 e M 2 S D 2 2 210 2 4 48 2 9 21 2 2 2 1 0 1 5 49 2 9 21-2 2 2 1 0 2 3 49 2 10 20 2 2 2 1 0 1 4 50 2 10 20 2 2 2 1 0 2 2 50 2 11 19 2 2 2 1 0 1 3 51 2 11 19 2 2 2 1 0 2 1 51 2 14 14 2 2 2 1 0 1 2 52 2 14 14 2 2 2 1 0 4 22 32 2 1 N 2 1 1 1 0 3 23 33 2 1 29 2 1 1 1 0 4 15 37 2 2 28 2 1 1 1 0 3 16 30 2 2 2O 2 1 1 1 0 4 12 40 2 3 27 2 1 1 1 0 3 13 41 2 3 27 2 1 1 1 0 4 11 41 2 4 24 2 1 1 1 0 3 12 42 2 4 26 2 1 1 1 0 4 10 42 2 5 25 2 1 1 1 0 3 11 43 2 5 25 2 1 1 1 0 4 7 4 2 4 N 21110 3 0 4 2 4 N 21110 4 4 4 2 7 2 21110 3 7 02 723211104 5472 822211103 4402 82221110 4 4 # 2 9 M 21110 3 5 # 2 9 2 21110 4 3 # 210 N 21110 3 45021020211104 25021119211103 3512111921110 4 1 51 2 14 16 2 1 1 1 0 3 2 52 2 14 14 2 1 1 1 9 M EM 22
TAOLE 6.5 2-3 stlE.-18 (ItNL-2 IEFF (ItlE.-1 NSE 34 263-274 (1968P) SCALE NOKL 278ROUPWF4 171 IEN0 MEDIUM 10 F235 1 0. 4.0066-5 E 2 F 238 1 0. 2.007-6 END F234 1 0. 5.30-7 END U-236 1 0 1.30-7 E G N 1 0. 1.869-4 END 0 1 0. 0.033736 En H 1 0. 0. W 228 EG
!$N=12 !!Ms40 ICN=70 105:1 En EFF ORNL-1 NSE 34 263-274 (1968P) SCALE NOKL 15.0 103 300 3 0 0 0 0 0 WERE 134.5948 -0 5 END E OMETRY EE ENO EFF ORNL-2 NSE 34 263-274 (1968P) SCALE MODEL 278ROUPDF4 1 8 1 INF)DIMEDIUM 10 U-235 1 0. 5 6205-5 E E U-238 1 0. 3 28-6 END U-234 10. 6.31-7 EE U-236 1 0. 1.63-7 END N 1 0. 2.129-4 END 0 1 0. 0.0338 E E H 1 0. 0. W 148 E G l 10 1 0. 1.0206-6 EE ISW 12 11> 40 IC* 70 IUS=1 E2 EFF ORNL-2 NSE 34 263-274 (1968P) SCALE NOKL 15.0103300300000 IPERE 134.5948 -0.5 EE EDETRY END KENO 1
23
r l
~
TABLE 6.5.2-4 PIL-1 1 M-2 EF PIL-1 IISE 25165 (1966) 270ROLPSF4 151 IIFH0 MEDIUM 10 PU-239 10. 9.373-5 BD l
PU-240 10. 4.501-6 DD N 10. 6.216-4 DID 0 1 0. 0.03456 END N 1 0. 0.06563 END ISN=12 IIM=40 IC#=70 IUS=1 ES E F PNL-1 NSE 25 165 (1966) 15 103 300 3 0 0 0 0 0 SPHERE 1 19.509 -0.5 EE E OMETRY DD KENO E F PNL-2 NSE 25 165 (1966) 276ROUPNDF4 1 5 1 INFNOMMEDIUM 10 PU-239 1 0. 4 141-4 END PU-240 1 0 1.908-5 END N 1 9. 4.720-3 END 0 1 0. 0.03977 END N 1 0. 0.05416 E G ISN=12 IIM:40 ICM:70 105:1 E 2 E T PNL-2 NSE 25 165 (1966)
- 15. 103 300 3 0 0 0 0 0 SPERE 119 509 -0.5 E2 EDETRY EMD KEND 24
e TA9'.E 6.5.2-5 BW UO2 8 22 EXPERIENTS B W UD2 EXP ELL SCALE M L E M FB-IV LA1TICE SELF9LD -
270ROUPSF4 3 7 3 LATTIKELL 00 0
1 0. 4.472735-2 EG p 235 1 6 5.570200-4 E E U-238 1 0. 2.100690-2 E E AL 2 0. 6.051481-2 E2 H
3 0. 6.668320-2 END l-10 3 0. 2.243000-5 ED 0
3 0. 3.334160-2 EM SOUAREPITCH 1.6254 1.0434 1 3 1.2060 2 E2 BW 002 EXP CELL SCALE MODEL EMBFB-IV LATTICE SELFSHLD
- 15. 103 300 3 # 1 1 6R1 CYLIBER 1.521716.8128.8128
.5 CYLINDER 2.603
.3128.8128
.5 CUB 0ID 3.8128
.0128.8128
.8128.0128.8128
.5 E2 GEOMETRY END KENO S W E 02 EXPERI M SCALE MODEL LATTI E CELL SELFSHIELDIN 278ROUP O F4 3 12 3 LATTI E CELL 00 0
1 0. 4.358350-2 EE U-235
- 10. 1.543510-4 E E U-238 1 0. 2.131190-2 E E PU-239 1 0. 2.646750-4 END PU-240 1 0. 5.295900-5 END PU-241
- 10. 5.271000-6 END PU-242 1 0. B.320000-7 END AM-241 1 0. 1616000-6 END ZIRCALLOY 2 1 019225 EE N
3 0. 6.668320-2 END B-10 3 0. 2 465000-5 END 0
3 0. 3.334140-2 E B SOUAREPITCH 1.89730 1.2751 1 3 1.4275 2 END BW W02 EXPERIM SCALE MODEL LATTIE SLF98. DING l
- 10. 103 300 3 #1 1 B1 CYLIGER 1.63754.94869.94069
.5 CYLISER 2.71374
.94069
.94069
.5 l
CUIDID 3.94869.94869.94069.94069.94869
.94069.5 En sEOMETRY WM 25
TABLE 6.5.3-1 K-Effective Results Computational Tool Evaluation SCALE Results Name of No. of Critical Neutron Experiment Feature K-eff 2 Sigma Histories ORN L-1 Fully Enriched 1.0021 ! 0.0060 30,000 ORNL-2 U-235 Nitrate 0.9977 0.0068 30,000 TRX-1 Low Enriched 0.9773 ! 0.0060 30,000 TRX-2 U-235 Rods 0.9820 ! 0.0060 30,000 PNL-1 Plutonium 1.0157 0.0108 30,000 PNL-2 Nitrate (5Pu240) 1.0105 0.0114 30,000 B&W UO Rod 0.9920*1 0.0046 30,000 B&W MO Rod 0.9972*! 0.0054 30,000
- k-infinity values 26 l
b
R
\\
e DOCKET NO.
[
CONTEDL NO._
M hk DATE OF DOC._ (( 6 DATE RCVD._
[d[O'7 [
' [/
FCUF PDR FCAF LPDR WM I&E REF.
' IGRIR SAFECUARDS FCTC OTiiER DESCRIPTION:
N WA juuddEdd&
/d b Afr s w i t, dd&So M ot h /rc 1am a &oe i r
l' f f
-