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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.
H. J. Petroski
Nuclear Technology | Volume 35 | Number 3 | October 1977 | Pages 671-676
Technical Note | Reactor | doi.org/10.13182/NT77-A31876
Articles are hosted by Taylor and Francis Online.
The strength of a reactor subassembly duct depends on its cross section and its material properties. Straight- and curved-beam theories have been used to analyze ducts with elastic-perfectly-plastic material behavior, and this analysis has been found to be suitable and convenient for parametric studies. The strengths of hexcans with different corner radii have been compared, and the stiffening effect of increasing radius has been quantified. The relative strengths of different duct cross sections have also been determined.