Spent Nuclear Fuel and Graphite Management for Salt-Cooled Reactors: Storage, Safeguards, and Repository Disposal
作者： Charles Forsberg , Per F. Peterson
DOI: 10.13182/NT14-88
关键词:
摘要: The fluoride salt–cooled high-temperature reactor (FHR) is a new type that combines the graphite-matrix coated-particle fuel and graphite moderator from gas-cooled reactors...
ans.org参考文章(12)
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