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Simulation approach and code functionality assessment using deterministic and Monte Carlo codes system for U-235 core-follow depletion calculation
Progress in Nuclear Energy ( IF 3.3 ) Pub Date : 2020-11-01 , DOI: 10.1016/j.pnucene.2020.103501
Mohammed Alqahtani , Adriaan Buijs , S.E. Day

Abstract Improving the performance of reactor simulation codes and adequately predicting the fuel composition are crucial to increase the accuracy of simulations and the quality of the analysis. McMaster Nuclear Reactor (MNR) follows a strict daily operational and shutdown schedule, except for Sundays. This results in a buildup of neutron poison during the reactor shutdown and hence the Control Rods (CRs) are extracted in the time of the reactor startup. Therefore, tracking MNR core composition using faithful Control Rods (CRs) positions data to estimate the axial fuel inventory profile is not yet established. In this study, nodal diffusion (OSCAR-4) and Monte Carlo (Serpent-2) simulations codes were employed. This study investigates: (1) code-to-code differences in the multiplication factor (keff) and in the axial fuel inventory considering the same burnup step sizes and total energy release with all CRs out; (2) for long cycles of core calculation, Monte Carlo stochastic code is computationally expensive, therefore an adequate temporal discretization steps are studied and identified. The keff values for the fresh reactor when all rods are out is: 1.1339 and 1.1283, and the results at the end of the burnup calculation is: 1.0101 and 1.0049, for Serpent-2 and OSCAR-4, respectively. In addition, the findings showed that averaging the CRs travel distance, for calculation the fuel inventory, can provide results similar to those with most tracked CRs motion.

中文翻译:

使用确定性和 Monte Carlo 代码系统进行 U-235 核心跟随损耗计算的仿真方法和代码功能评估

摘要 提高反应堆模拟程序的性能和充分预测燃料成分对于提高模拟精度和分析质量至关重要。麦克马斯特核反应堆 (MNR) 遵循严格的每日运行和关闭时间表,周日除外。这会导致反应堆停堆期间中子毒物的积累,因此在反应堆启动时取出控制棒 (CR)。因此,还没有建立使用可靠的控制棒 (CR) 位置数据来估计轴向燃料库存剖面的 MNR 堆芯成分。在这项研究中,采用了节点扩散 (OSCAR-4) 和蒙特卡罗 (Serpent-2) 模拟代码。本研究调查:(1) 考虑到相同的燃耗步长和所有 CR 的总能量释放,乘法因子 (keff) 和轴向燃料库存的代码到代码差异;(2) 对于长周期的核心计算,蒙特卡洛随机码的计算成本很高,因此研究并确定了足够的时间离散化步骤。当所有棒​​都用完时,新反应堆的 keff 值为:1.1339 和 1.1283,燃耗计算结束时的结果分别为:Serpent-2 和 OSCAR-4 的 1.0101 和 1.0049。此外,研究结果表明,平均 CRs 行进距离,用于计算燃料库存,可以提供类似于大多数跟踪 CRs 运动的结果。Monte Carlo 随机代码在计算上是昂贵的,因此研究和确定了足够的时间离散化步骤。当所有棒​​都用完时,新反应堆的 keff 值为:1.1339 和 1.1283,燃耗计算结束时的结果分别为:Serpent-2 和 OSCAR-4 的 1.0101 和 1.0049。此外,研究结果表明,平均 CRs 行进距离,用于计算燃料库存,可以提供类似于大多数跟踪 CRs 运动的结果。Monte Carlo 随机代码在计算上是昂贵的,因此研究和确定了足够的时间离散化步骤。当所有棒​​都用完时,新反应堆的 keff 值为:1.1339 和 1.1283,燃耗计算结束时的结果分别为:Serpent-2 和 OSCAR-4 的 1.0101 和 1.0049。此外,研究结果表明,平均 CRs 行进距离,用于计算燃料库存,可以提供类似于大多数跟踪 CRs 运动的结果。
更新日期:2020-11-01
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