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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.
Prodyot Roy, Douglas N. Rodgers
Nuclear Technology | Volume 39 | Number 2 | July 1978 | Pages 213-215
Technical Note | Analysis | doi.org/10.13182/NT78-A32080
Articles are hosted by Taylor and Francis Online.
It has been observed that in sodium-heated steam generators most of the hydrogen produced from water- or steam-side corrosion permeates into the secondary sodium. The amount of hydrogen that diffuses into the secondary side is extremely important from the standpoint of the design of the cold trap, hydrogen background levels, and tritium concentrations in the secondary system. We have compiled all the available data on H2 permeation from all operating sodium-heated steam generators. In addition, based on the available steam-side corrosion data, we have made tentative recommendations: Steady-state H2 flux: