摘要
钍基熔盐堆因其在安全性、经济性及可持续性方面的优势被列为第四代核能系统重点发展的堆型。我国已经开展了相关的研究,然而国内关于研究堆的法规导则不完整,相关规定和要求比较原则,必须结合钍基熔盐研究堆的特点进行具体研究。针对固态燃料钍基熔盐实验堆,从核安全评审的角度,对核安全评审相关的问题进行深入研究分析。依据NRC针对下一代先进核能系统制定的评审方法,充分调研轻水动力堆(压水堆、沸水堆)、正在运行的研究堆、以及同样被列为第四代反应堆重点发展堆型的钠冷快堆、高温气冷堆,参考国内外对上述堆型堆芯核设计限值的确定原则及相关依据,初步给出钍基熔盐堆堆芯核设计关键安全限值。
Thorium molten salt reactor has been listed as a key development of the fourth generation nuclear power system because of its advantages in safety,economy and sustainability. China has carried out the relevant research,however,the domestic regulations on the research reactor is not complete. The problem of the nuclear safety review is analyzed in depth from the point of view of the nuclear safety review. This study is based on NRC＇s review of the next generation of advanced nuclear energy systems,fully research light water power reactor（ PWR,BWR）,running research reactor,sodium cooled fast reactor,and high temperature gas cooled reactor. On the basis of the determination of the design limits of the core design,the key safety margins for the design of the thorium molten salt reactor are given.
出处
《科学技术与工程》
北大核心
2016年第3期179-182,共4页
Science Technology and Engineering
基金
中国科学院战略性先导科技专项(XDA02050500)资助
关键词
钍基熔盐堆
安全评审
关键安全限值
thorium molten salt reactor
safety review
safety margin
