= TS 
Wastes Depend on Reactor System: In order to define the wastes more 
specifically, it is necessary to assume a particular reactor system with 
its associated chemical plant. Following are two different assumptions: 
Case 1. Natural Uranium: 
The reactor contains the 100 kg of yo3? in natural uranium 
(mixture of 738 and y°3°). Such a reactor would produce 
pu-2?, Assume that 1 gram of Pu is produced per gram of 
yo? burned. The irradiated fuel from such a reactor would 
then contain the following after approximately 30% burnup: 
Per 1 kg yo? 235 
Charged or 139 kg Per gram U 
natural U charged Consumed, fission + capture 
Total U ALAS BN Tee ~ 465 gm/em 
Pu _~ 300 grams — 1 gram/gm 
FP, inactive + active — 265 grams ~ 0.88 gram/gm 
*FP active ~ 32.5 grams ~0O.11 gram/gm 
*FP active B -~ 220,000 curies _ 735 curies/gm 
* 100 days cooling 
Case 2. WNon-breeding Reactor: 
235 
The reactor uses enriched U as fuel with no fertile material. 
Here the irradiated fuel would contain the following after 30% : 
burnup: 
DECLASSIFIED 
