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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.
N. Ketzlach
Nuclear Technology | Volume 42 | Number 1 | January 1979 | Pages 65-70
Technical Paper | Chemical Processing | doi.org/10.13182/NT79-A32162
Articles are hosted by Taylor and Francis Online.
Subcommittee 8 of the Standards Committee of the American Nuclear Society has conducted the prescribed five-year review and update of ANSI N16.4-1971, which provides guidance for the use of borosilicate glass Raschig rings as a neutron absorber in solutions of highly enriched fissile materials. The proposed revision to the Standard extends its application to low enriched 235U fuels based on the 235U concentration in the vessel and to a limited range of alkaline environments. It incorporates standard American Society for Testing and Materials chemical acceptance tests for the glass, a chemical acceptance test for its acceptability in an alkaline environment, and a test that provides information on volume loss due to chemical reaction in addition to that due to settling.