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Code development and safety analyses for Pb-Bi-cooled direct contact boiling water fast reactor (PBW
  • ISSN号：0149-1970
  • 期刊名称：Progress in Nuclear Energy
  • 时间：2013.9.9
  • 页码：177-187
  • 相关项目：新概念铅铋合金冷却快堆的热工水力基础问题研究
作者： Su, G. H.|Wang, J.|Tian, W. X.|Qiu, S. Z.|
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新概念铅铋合金冷却快堆的热工水力基础问题研究
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