Neutron flux calculation of reactor pressure vessel for MOX fuel core
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摘要: 对含MOX燃料堆芯的压力容器(RPV)快中子注量率计算进行了初步研究,探讨了适用于MOX堆芯方案屏蔽计算的堆芯源项处理方法。采用三维离散纵标程序TORT,针对CAP1400型堆芯装载50%MOX燃料方案开展了RPV快中子注量计算,结果表明：堆芯装载50%MOX燃料可满足RPV屏蔽安全设计要求；对比分析含MOX堆芯方案和全UO2堆芯方案的RPV快中子注量率的特性差异,从RPV辐射防护最优化的角度,后续燃料管理方案优化时可重点关注关键位置处组件的布置。Abstract: The reactor pressure vessel (RPV) neutron flux calculation method for MOX fuel core was preliminarily researched, especially the core source calculation method for MOX fuel core. Based on three-dimensional discrete ordinate code TORT, the RPV fast neutron flux was calculated for CAP1400 reaction core carrying 50% MOX fuel, and the difference between MOX fuel core and UO2 fuel core was compared and analyzed. The results demonstrate that CAP1400 reaction core carrying 50% MOX fuel can satisfy the request of the radiation safety of RPV. For radiation shielding optimization, the suggestion is that much attention should be paid to the core loading pattern selection for the pivotal position.
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Key words:
- MOX fuel /
- reactor pressure vessel /
- fast neutron flux /
- TORT
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