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Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
Hsiang-Shou Cheng, David J. Diamond, Ming-Shih Lu
Nuclear Technology | Volume 37 | Number 3 | March 1978 | Pages 246-260
Technical paper | Reactor | doi.org/10.13182/NT78-A31993
Articles are hosted by Taylor and Francis Online.
An extensive study of boiling water reactor scram reactivity behavior is presented. It is based on a spacetime analysis using a two-dimensional (R,Z) dynamics code that includes a two-phase thermal-hydraulics model. Calculations were made of the sensitivity of scram to such physical quantities as initial control rod position and power distribution, scram speed, system pressure, and varying inlet flow rate and temperature. The end-of-cycle Haling operating condition with all rods initially withdrawn was found to give rise to the limiting scram reactivity function. Calculations were also made to find the effect on scram of commonly used modeling approximations. These included the effect of neglecting delayed neutrons (conservative), using a time invariant void distribution (nonconservative), and defining point kinetics parameters in terms of different weighting functions. The importance of defining these parameters consistent with their use in plant transient analyses was also demonstrated.