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MCS – A Monte Carlo particle transport code for large-scale power reactor analysis
Annals of Nuclear Energy ( IF 1.9 ) Pub Date : 2020-05-01 , DOI: 10.1016/j.anucene.2019.107276
Hyunsuk Lee , Wonkyeong Kim , Peng Zhang , Matthieu Lemaire , Azamat Khassenov , Jiankai Yu , Yunki Jo , Jinsu Park , Deokjung Lee

Abstract A new Monte Carlo (MC) neutron/photon transport code, called MCS, has been developed at Ulsan National Institute of Science and Technology (UNIST) with the aim of performing the high-fidelity multi-physics simulation of large-scale power reactors, especially pressurized water reactors (PWR). The high-fidelity multi-physics analysis of large-scale PWR is a challenging problem due to two aspects, the first being the difficulty of implementing various state of the art techniques into a single code system, and the other making it feasible to run such simulations on practical computing machines within reasonable amount of memory usage and computing time. In this paper, features implemented into MCS for large-scale PWR simulations are described including but not limited to depletion, thermal/hydraulics coupling, fuel performance coupling, equilibrium xenon, on-the-fly neutron cross-section Doppler broadening, and critical boron search. The efficient memory usage for burnup simulation and the high performance of MCS through various algorithms and optimizations (parallel fission bank, hash indexing) are illustrated on Monte Carlo performance benchmarks. Finally, the large-scale PWR analysis capability is fully demonstrated with BEAVRS Cycles 1 & 2 calculations.

中文翻译:

MCS – 用于大型动力反应堆分析的蒙特卡罗粒子传输代码

摘要 蔚山国立科学技术研究院 (UNIST) 开发了一种新的蒙特卡洛 (MC) 中子/光子传输代码,称为 MCS,旨在对大型动力反应堆进行高保真多物理场模拟。 ,尤其是压水反应堆(PWR)。由于两个方面的原因,大规模压水堆的高保真多物理分析是一个具有挑战性的问题,第一个是将各种最先进的技术实现到单个代码系统中的难度,另一个使得运行这样的系统变得可行在合理的内存使用量和计算时间内对实际计算机进行模拟。在本文中,描述了在 MCS 中实现的用于大规模 PWR 模拟的功能,包括但不限于损耗、热/水力耦合、燃料性能耦合、平衡氙、动态中子截面多普勒展宽和临界硼搜索。Monte Carlo 性能基准测试说明了燃耗模拟的有效内存使用和 MCS 通过各种算法和优化(并行裂变库、哈希索引)的高性能。最后,通过 BEAVRS Cycles 1 & 2 计算充分展示了大规模 PWR 分析能力。
更新日期:2020-05-01
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