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CODE TO CODE VALIDATION OF SAC-3D BASED ON EBR-II BENCHMARK PROBLEM

机译:基于EBR-II基准问题的SAC-3D代码验证的代码

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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.
机译:很多以前的工作表明,三维中子计算模块可以提供特别是在一些预期瞬态事故反应堆系统安全分析更好的预测结果与强烈的空间影响因素。 SAC-3D代码是SAC系列反应器系统安全分析代码的新版本,其是由中国北方电力大学[4] [5] [6] [7]开发。在这个版本中,该中子计算模块基于所述三维节点展开法显影。在2012年,IAEA草签流的EBR-II损失基准分析一个CRP不紧急停堆测试,SHRT-45R的基准数据是由提供ANL基准规范之一。在目前的工作,EBR-II SHRT-45R的中子学基准问题与SAC-3D分析。 SAC-3D的中子计算模块是由关键结果与基准数据进行比较验证。仿真结果也与此CRP的其他参与者所提供的结果相吻合。

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