基于EBR-II基准问题的SAC-3D代码对代码验证

D. Lu, Lyu Siyu, D. Sui
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引用次数: 0

摘要

大量前期工作表明,三维中子计算模块在反应堆系统安全分析中具有较好的预测效果,特别是在若干具有较强空间影响因素的预期瞬态事故下。SAC- 3d规范是华北电力大学[4][5][6][7]开发的SAC系列反应堆系统安全分析规范的新版本。在该版本中,基于三维节点展开法开发了中子计算模块。2012年IAEA启动了EBR-II无停堆失流试验基准分析CRP, SHRT-45R基准数据是ANL提供的基准规范之一。本文利用SAC-3D软件对EBR-II SHRT-45R的中子基准问题进行了分析。通过与基准数据的对比,验证了SAC-3D的中子计算模块。模拟结果与该CRP的其他参与者提供的结果也很吻合。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Code to Code Validation of SAC-3D Based on EBR-II Benchmark Problem
A lot of previous works indicated that the 3D neutronics calculation module can provide better prediction results in reactor system safety analysis especially under several anticipated transient accidents which with strong spatial influence factors. SAC-3D code is a new version of SAC series reactor system safety analysis codes which was developed by North China Electric Power University[4][5][6][7]. In this version, the neutronics calculation module was developed based on the three-dimensional nodal expansion method. In 2012, IAEA initialed a CRP on benchmark analysis of EBR-II loss of flow without scram test, SHRT-45R benchmark data is one of the benchmark specifications provided by ANL. In the present work, the neutronics benchmark problem of EBR-II SHRT-45R was analyzed with SAC-3D. The neutronics calculation module of SAC-3D was validated by comparing the key results with the benchmark data. The simulation results also agreed well with the results provided by other participants of this CRP.
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