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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.
K. Takeuchi
Nuclear Technology | Volume 39 | Number 2 | July 1978 | Pages 155-166
Technical Paper | Reactor | doi.org/10.13182/NT78-A32075
Articles are hosted by Taylor and Francis Online.
The computer code MULTIFLEX was developed to take into account hydro-structural interactions in the hydraulic force calculation for structural integrity evaluation of a pressurized water reactor primary system during a transient induced by a loss-of-coolant accident. Code verification was performed by analyzing the fundamental phenomena pertinent to the mutual interaction between the hydraulic and the structural systems. Phenomena investigated were the virtual mass effect of reducing the in-air structural frequency to the in-water frequency, the fluid compression effect due to structural deformation, and the effective sonic velocity for hydraulic pressure wave propagation. Experiments emphasizing each aspect of the phenomena were selected and analyzed. In the analyses, the independent mass model for the structural dynamics was exclusively employed. Satisfactory agreement between the analyses and the experimental data was obtained.