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Relative safeguards risks of advanced reactor concepts. [Material diversion in fuel cycle for seven reactor concepts]

Conference · · Nucl. Mater. Manage.; (United States)
OSTI ID:7343899
The purpose of this report is to develop a procedure to quantitatively assess the risk to diversion of the nuclear material in the fuel cycle for seven advanced reactor design concepts (LWR-Pu, LMFBR, HTGR, GCFR, MSBR, LWBR, HWR). Each stage in each of the seven reactor fuel cycles is evaluated and the result of the evaluation is a comparison among the various fuel cycles. This method of evaluation is used to determine the stages in a nuclear reactor fuel cycle that are most susceptible to diversion; it also gives an indication of what factors contribute to that susceptibility.
Research Organization:
Ohio State Univ., Columbus
OSTI ID:
7343899
Conference Information:
Journal Name: Nucl. Mater. Manage.; (United States) Journal Volume: 5:3
Country of Publication:
United States
Language:
English