RELATIVE SAFEGUARDS RISKS OF ADVANCED REACTOR CONCEPTS

Year
1976
Author(s)
C.B. Franklin - The Ohio State University
F.A. O'Hara - The Ohio State University
Abstract
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. 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.