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基于蒙特卡罗-离散纵标双向耦合方法的堆坑粒子注量率计算 被引量:1

Particle Fluence Rate Calculation of Reactor Pit Based on MC-S_N Bidirectional Coupled Method
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摘要 为有效解决大型复杂核设施屏蔽计算问题,研究了三维蒙特卡罗(MC)-离散纵标(SN)双向耦合方法,通过自主开发接口程序实现MC粒子概率分布与SN角通量密度之间的相互转换,实现MC-SN双向耦合计算。将基于MC-SN双向耦合方法的程序用于某反应堆堆坑底部粒子注量率计算。利用MC程序建立堆芯及堆坑处的精细模型进行计算,三维SN程序用于堆芯下表面与压力容器底面之间区域的计算。通过MC-SN-MC两步耦合计算,给出堆坑通道及小室内的中子和光子注量率。三维MC-SN双向耦合方法计算结果与单一MCNP程序结果吻合较好,初步验证了该方法是解决大型复杂核装置屏蔽问题的有效工具。 In order to effectively solve the shielding problem with complex geometric and bulk shields of nuclear facility ,the three-dimensional Monte Carlo (MC)-discrete ordi-nates (SN ) bidirectional coupled method was developed .The transform between particle probability distribution of MC and angle flux density of SN was realized by a self-devel-oped interface program to achieve the coupling calculation . The test calculation was taken by the application of the MC-SN bidirectional coupled method on the particle fluence rate calculation of reactor pit bottom .Monte Carlo code was employed to accu-rately simulate the structure of core and the model of reactor pit ,while the 3D SN code was used for the calculation from the core bottom surface to the pressure vessel bottom region .Neutron and photon fluence rates of reactor pit channel and indoor were calcu-lated by MC-SN-MC two step coupled method .The calculation results were compared with results of MCNP and satisfactory agreements were obtained .The results demon-strate that the method is an effective tool to solve the shielding problem of large complex shielding of nuclear facility .
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2014年第9期1621-1626,共6页 Atomic Energy Science and Technology
基金 国家自然科学基金面上项目资助(11275070) 教育部新世纪优秀人才支持计划资助项目(NCET-11-0631)
关键词 蒙特卡罗 离散纵标 双向耦合方法 堆坑 Monte Carlo discrete ordinates bidirectional coupled method reactor pit
作者简介 韩静茹(1983-),女,河北保定人,工程师,博士,反应堆物理与辐射屏蔽专业
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参考文献6

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