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大型压水堆装载50% MOX燃料方案初步研究

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大型压水堆装载50% MOX燃料方案初步研究 第35卷第2期 2015年6月
核科学与工程
Nuclear Science and Engineering
Vol.35No.2
Jun.2015
大型压水堆装载50%M0X燃料
方案初步研究刘婵云,毕光文,杨波(上海核工程研究设计院,上海200233)
摘要:在保持堆内构件设计、燃料组件机械设计以及控制棒设计和布置不变的前提下,对大型压水堆应用MOX燃料进行初步研究。在遵守与UO,堆芯相同的核设计准则的基础上,开展装载50%MOX燃料的堆芯燃料管理方案研究及核特性分析。分析结果表明,堆芯主要物理参数满足设计准则要求,能够实现堆芯运行和控制相关要求,具备装载50%MOX燃料的能力。混合堆芯的有效缓发中子份额比
UO堆芯有所减小,其对弹棒事故的影响应予以重点关注。关键词:压水堆;MOX燃料;堆芯设计;核特性评估
中图分类号:TL329
文章标志码:A
文章编号:0258-0918(2015)02-0314-06
PreliminaryStudyonCoreDesignwith50%MOXFuelinPWRs
LIUChan-yun,BIGuang-wen,YANGBo
(Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China)
Abstract:Core design optimization for MOX fuel is an important aspect for new generation light water reactor.The purpose of this paper is to demonstrate that the193-assembly two-loop pressurized water reactor studied is capable for MOx utilization without significant changes to the design of the plant including core internal design, fuel assembly mechanical design, control rod design and pattern. A mixed 5o% MOX/UO core are designed and investigated by comparing with a 1oo% UOz core. The MOX fuel utilization has impacts on the nuclear characteristic parameters, but the nuclear and safety criteria same as that considered in the UO, core design are all satisfied and the operating flexibility is not sacrificed. Because the effective delayed neutron fraction (βe) of MOX-beard core is lower than that of the 1oo% UO, core, much attention should be paid to the impact on the related analysis especially to the control rod ejection accident. Key words:PWR;MOX fuel; core design; nuclear characteristic
收稿日期:2014-09-02:修回日期:2014-12-29
作者简介:刘婵云(1983一),女,江西上饶人,工程师,硕士,现主要从事反应堆物理设计工作 314
上一章:CPR1000项目LSS系统设计研究 下一章:改进的源倍增方法测量控制棒价值

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