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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.
Sunghwan Yun, Nam Zin Cho, Mu-Young Ahn, Seungyon Cho
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 232-238
Tritium, Safety, and Environment | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8908
Articles are hosted by Taylor and Francis Online.
The Korean HCSB (Helium Cooled Solid Breeder) TBM (Test Blanket Module), whose breeding zone is composed of lithium ceramic, beryllium and graphite in pebble form, was designed based on LOCAL assumption. In this research, we establish a simple preliminary GLOBAL neutronics model for the Korean HCSB TBM and perform neutronics analyses including depletion (transmutation) calculation during 500EFPDs (Effective Full Power Days) using the modified MONTEBURNS code. The neutronics characteristics for D-D plasma phase are investigated in the preliminary GLOBAL neutronics model, and the results are compared with those of D-T plasma phase. Moreover, we also establish the A-lite based GLOBAL neutronics model for more reliable neutronics calculation, and the results are compared with each other.