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Materials to be Dissolved
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Guidelines For Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities
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Dissolution Process


DOE-STD-3007-93
Table 1. Materials to be Dissolved (Based on Ref. 15)
Weights in Kg
Diameter
Items
Length
Total U
U-235al Pu
Tot
Equivalent
Fuel
U-235
Enrichment
EBR-II
1 bundle
14'2.25"
6.469" OD
285
0.628
0.789
0.77 %
TRR
54 bundles
131"
2.75" ID
2758
17.02
2.341
0.79 %
TRR
27 bundles
131"
4.00" ID
1180
7.299
0.985
0.78 %
Total:
82 bundles
4223
24.95
4.115
0.78 %
Table 2. Number of Bundles Loaded During Each Batch
Entire
First Port
Second Port
Third Port
Fourth Port
Dissolver
Batch
TRR
EBR-II
TRR
EBR-II
TRR
EBR-II
TRR
EBR-II
TRR
EBR-II
1
6
0
6
0
6
0
3
0
21
0
2
6
0
6
0
6
0
3
0
21
0
3
6
0
6
0
6
0
0
1
18
1
4
6
0
6
0
6
0
3
0
21
0
Total
81
1
Table 3. Heavy Metal Loadings Per Port
Batches
Fuel
Loadings Per Port (kg)
Equivalent
Equivalent
Type of
That Insert
Fuel in
Type
U-235
U-235
Insert
Are Present
Insert
Assumed
Total U
Pu-239
Loading
Enrichment
Mark-42
1, 2, 3, 4
TRR
Average
291.7
1.802
0.246
2.29
0.79 %
Max. Pu
320.9
2.310
0.474
3.26
1.01 %
3-Well
1, 2, 4
TRR
Average
145.9
0.901
0.123
1.15
0.79 %
Max. Pu
160.5
1.155
0.237
1.63
1.01 %
No Insert
3
EBR-II
Total
285
0.628
0.789
2.21
0.77 %
Table 4. Average Loadings Per Batch
Average Loadings Per Batch (kg)
Equivalent
Equivalent
U-235
U-235
Batch
Total U
U-235
Pu-239
Loading (kg)
Enrichment
1
1021.0
6.305
0.862
8.03
0.79 %
2
1021.0
6.305
0.862
8.03
0.79 %
3
1160.0
6.033
1.528
9.09
0.78 %
4
1021.0
6.305
0.862
8.03
0.79 %
Total
4223.0
24.95
4.115
33.18
0.78 %
6-8


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