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Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from a Pre-Konvoi PWR reactor
Nuclear Engineering and Design ( IF 1.7 ) Pub Date : 2021-04-20 , DOI: 10.1016/j.nucengdes.2021.111173
Manuel García , Yurii Bilodid , Joaquín Basualdo Perello , Riku Tuominen , Andre Gommlich , Jaakko Leppänen , Ville Valtavirta , Uwe Imke , Diego Ferraro , Paul Van Uffelen , Marcus Seidl , Victor Sanchez-Espinoza

The focus of this work is the validation of Serpent-SUBCHANFLOW-TRANSURANUS, a high-fidelity multiphysics system coupling Monte Carlo neutron transport, subchannel thermalhydraulics and fuel-performance analysis. A full-core pin-by-pin burnup calculation for the first operating cycle of a Pre-Konvoi PWR plant is presented and the results are assessed using experimental data. The critical boron concentration and a set of pin-level neutron flux profiles are compared against measurements, with very good agreement. The impact of using fuel-performance analysis is discussed comparing the results obtained with the three-code coupling with the ones using the traditional neutronic-thermalhydraulic approach. The studies presented here are part of the final stage of the EU Horizon 2020 McSAFE project, closing the development cycle of the Serpent-SUBCHANFLOW-TRANSURANUS system, from implementation to validation.



中文翻译:

使用Pre-Konvoi PWR反应堆的实验数据验证蛇-SUBCHANFLOW-TRANSURANUS引脚到引脚的燃耗计算

这项工作的重点是对蛇-SUBCHANFLOW-TRANSURANUS的验证,Serpent-SUBCHANFLOW-TRANSURANUS是一个高保真多物理场系统,结合了蒙特卡洛中子传输,子通道热工水力和燃料性能分析。给出了Pre-Konvoi PWR工厂第一个运行周期的全内核逐引脚燃耗计算,并使用实验数据评估了结果。将临界硼浓度和一组pin级中子通量曲线与测量结果进行了比较,具有很好的一致性。讨论了使用燃料性能分析的影响,将通过三代码耦合获得的结果与使用传统中子-热工液压方法得到的结果进行了比较。此处介绍的研究是“欧盟地平线2020 McSAFE”项目最后阶段的一部分,

更新日期:2021-04-20
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