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超临界水冷快堆增殖因子敏感性初步研究

Three-Dimensional Core Preliminary Analysis on Breeding Capability of Super Fast Reactor
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摘要 从长远观点来看,超临界水冷快堆(SCFWR)的增殖性能是一个重要问题,由于超临界水堆中冷却剂密度仅相当于当前沸水堆(BWR)的1/3,加之稠密性栅格布置,SCFWR具有增殖的潜力。为了探究SCFWR的增殖性问题,利用基于多群三维细网有限差分中子扩散方程的堆芯核计算方法,设计不同的算例,分别计算了堆芯冷却剂流型、不锈钢和ZrH1.7的利用、堆型布置、棒径大小、MOX燃料中PuO2的份额、堆芯燃耗深度及堆芯尺寸等因素对SCFWR增殖性能的影响。计算结果表明,增大堆芯转换比的途径有:采用对流式流型、加入ZrH1.7层、采用合适的堆芯布置、增加棒径、提高MOX燃料中PuO2的份额及增大堆芯尺寸而减少中子泄漏等。从而为提高SCFWR的转换比提供了可参考的依据路线。 From the long-term point of view,the breeding capability of the super fast reactor(SCFWR) is an important issue.SCFWR has the potential for proliferation,for the reason that the coolant density of the supercritical water reactor is only equivalent to 1/3 of that of the current boiling water reactor(BWR),coupled with the grid layout.In order to explore the proliferation of SCFWR,a multi-group 3-D diffusion core calculation methods based on the finite difference method were used.And a series of examples with different factors on the proliferation of SCFWR,such as,the core coolant flow type,the use of stainless steel and ZrH1.7,the type of reactor layout,fuel rod size,the share of PuO2 in the MOX,core burnup and core size,were calculated.As can be seen from the results,there are several ways to get greater core conversion ratio: adopting convection flow pattern,adding ZrH1.7,adopting the appropriate core layout,increasing the fuel rod diameter,increasing the share of PuO2 in the MOX and increasing the size of the core to decrease the core leakage and so on.The results of those calculations provide a reference basis for improving conversion ratio of the SCFWR.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2013年第B06期239-244,共6页 Atomic Energy Science and Technology
基金 国家自然科学基金资助项目(10976021) 国家863计划资助项目(2013AA051402)
关键词 超临界水冷快堆 增殖 转换比 冷却剂流型 堆型布置 super fast reactor breeding conversion ratio coolant flow pattern reactor layout
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参考文献4

  • 1OKUMURA K, KUGO T, KANEKO K, et al.SRAC2006: A comprehensive neutronics calculation code system[R]. Tokai-mura, Ibaraki, Japan: Department of Nuclear Energy System, Japan Atomic Energy Research Institute, 2006.
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