Comparison of potential radiological impacts of /sup 233/U and /sup 239/Pu fuel cycles
Nuclear fuel cycles utilizing /sup 233/U are currently the subject of considerable interest in the United States. This paper focuses on the identification of significant differences between the off-site radiological hazards posed by /sup 232/Th//sup 233/U (Th/U) and /sup 238/U//sup 239/Pu (U/Pu) fuel cycles, and represents a portion of our involvement in the Nonproliferation Alternative Systems Assessment Program (NASAP), to be used in support of the International Fuel Cycle Evaluation (INFCE). The major contributors to radiological dose are likely to be uranium mining and milling (58.5% of total fuel cycle dose), reprocessing (33.9%), and light-water reactor power generation (7.3%). The remainder of the cycle, including enrichment processes, fuel fabrication, transportation, and waste management, contributes only 0.3% to total estimated fuel cycle dose.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5596240
- Report Number(s):
- CONF-791103-101
- Country of Publication:
- United States
- Language:
- English
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