基于钠冷快堆BN-600的SuperMC基准校验分析

Benchmarking of SuperMC Based on Sodium Cooled Fast Reactor BN-600

  • 摘要: 超级蒙特卡罗核模拟软件SuperMC是由FDS团队自主研发的一个通用的多物理耦合蒙特卡罗模拟程序,基于蒙特卡罗与确定论耦合方法并集成先进并行计算与减方差技术。最新版本SuperMC2.2支持中子、光子、中子光子耦合输运,实现了几何与物理的自动建模、输运计算、过程与计算结果可视化的集成计算分析。SuperMC2.2已通过国际临界安全基准实验手册(ICSBEP)、国际屏蔽积分泄漏率实验手册(SINBAD)等大量国际基准例题的正确性验证。本文用IAEA发布的钠冷快堆BN-600基准例题进一步进行测试校验,测试计算了有效增殖因数、多普勒系数、密度系数、膨胀系数等9个参数。结果显示,SuperMC2.2的计算结果与MCNP相比偏差均在1个标准差范围内,且基本在国际各研究机构计算结果之间,初步验证了SuperMC2.2应用于快堆中子输运计算中的准确性和可靠性。

     

    Abstract: Super Monte Carlo simulation program for nuclear and radiation process (SuperMC) is a general purpose, multi-physics Monte Carlo simulation code developed by FDS Team. It is based on hybrid Monte Carlo-deterministic method, with integrated parallel computation and variance reduction techniques. The latest version, SuperMC2.2, can perform neutron, photon and coupled transport with automatic modeling and visualized analysis capability. SuperMC 2.2 has already been validated with many benchmark cases from international criticality safety benchmark evaluation project and shielding integral benchmark archive and database etc. To further verify and validate the code, it was benchmarked with the BN-600 hybrid core model released by IAEA. Nine parameters, consisting of effective multiplication factor, Doppler coefficients, density coefficients and expansion coefficients, were calculated. In all cases, the difference between the results of SuperMC and MCNP are within one standard deviation and within the range of values of results calculated by other institutes. The correctness and reliability of SuperMC neutron transport in fast reactor are preliminarily verified.

     

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