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本课题是国家863重点项目“核燃料循环与核安全技术研究”其中的一个课题,由中国原子能科学研究院承担,清华大学、华北电力大学、西安交通大学和上海交通大学等协作。课题研究热堆核电站(压水堆、重水堆、高温气冷堆)和快堆核电站的燃料循环技术模式,分析各种燃料循环技
This project is one of the topics of National 863 Key Project “Research on Nuclear Fuel Cycle and Nuclear Safety Technology ”, which is undertaken by China Institute of Atomic Energy, Tsinghua University, North China Electric Power University, Xi’an Jiaotong University and Shanghai Jiaotong University. Research topics Reactor nuclear power plant (pressurized water reactor, heavy water reactor, high temperature gas-cooled reactor) and fast reactor nuclear fuel cycle technology model, analysis of various fuel cycle technology