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Uranium production in thorium/denatured uranium fueled PWRs

Technical Report ·
DOI:https://doi.org/10.2172/5412741· OSTI ID:5412741
Uranium-232 buildup in a thorium/denatured uranium fueled pressurized water reactor, PWR(Th), was studied using a modified version of the spectrum-dependent zero dimensional depletion code, LEOPARD. The generic Combustion Engineering System 80 reactor design was selected as the reactor model for the calculations. Reactors fueled with either enriched natural uranium and self-generated recycled uranium or uranium from a thorium breeder and self-generated recycled uranium were considered. For enriched natural uranium, concentrations of /sup 232/U varied from about 135 ppM (/sup 232/U/U weight basis) in the zeroth generation to about 260 ppM (/sup 232/U/U weight basis) at the end of the fifth generation. For the case in which thorium breeder fuel (with its relatively high /sup 232/U concentration) was used as reactor makeup fuel, concentrations of /sup 232/U varied from 441 ppM (/sup 232/U/U weight basis) at discharge from the first generation to about 512 ppM (/sup 232/U/U weight basis) at the end of the fifth generation. Concentrations in freshly fabricated fuel for this later case were 20 to 35% higher than the discharge concentration. These concentrations are low when compared to those of other thorium fueled reactor types (HTGR and MSBR) because of the relatively high /sup 238/U concentration added to the fuel as a denaturant. Excellent agreement was found between calculated and existing experimental values. Nevertheless, caution is urged in the use of these values because experimental results are very limited, and the relevant nuclear data, especially for /sup 231/Pa and /sup 232/U, are not of high quality.
Research Organization:
Oak Ridge Gaseous Diffusion Plant, Tenn. (USA)
DOE Contract Number:
W-7405-ENG-26
OSTI ID:
5412741
Report Number(s):
K/OP-241
Country of Publication:
United States
Language:
English