基于Monte Carlo方法的压水堆相关组件内热源计算与分析  

Calculation and analysis of heat source of PWR assemblies based on Monte Carlo method

作　　者：胡也[1] 陈义学[1] 杨寿海[1] 靳忠敏 

机构地区：[1]华北电力大学核科学与工程学院,北京102206 [2]国家核电软件技术中心,北京100029

出　　处：《核科学与工程》2013年第2期168-174,共7页Nuclear Science and Engineering

基　　金：教育部"新世纪优秀人才支持计划";中央高校基本科研业务费项目

摘　　要：堆芯中核燃料发生裂变时,伴随产生极强的中子及γ辐射,这些辐射在燃料组件中发生能量沉积,产生热应力、辐照损伤等诸多影响反应堆安全运行的因素。尤其对于新型含钆可燃毒物棒组件,国内对此方面的研究需要进一步开展。采用三维蒙特卡罗输运计算程序MCNP和基于ENDF/B的连续截面数据库,对压水堆18个月长、短周期装料方式的堆芯相关组件内热源的释热率分布进行详细计算,计算得出控制棒、阻力塞棒和新型含钆可燃毒物棒释热率精确计算值,并对不同版本数据库中部分关键核素截面对计算结果的影响进行比较分析,为核反应堆堆芯设计提供参考。When fission occurs in nuclear fuel in reactor core, it releases numerous neutron and γ radiation, which takes energy deposition in fuel components and yields many factors such as thermal stressing and radiation damage influencing the safe operation of a reactor. Using the three-dimensional Monte Carlo transport calculation program MCNP and continuous crosssection database based on ENDF/B series to calculate the heat rate of the heat source on reference assemblies of a PWR when loading with 18-month short refueling cycle mode, and get the precise values of the control rod, thimble plug and new burnable poison rod within Gd, so as to provide basis for reactor design and safety verification.

关 键 词：MCNP 释热率 含钆毒物棒 内热源 

分 类 号：TL32[核科学技术—核技术及应用]