高保真传输码预测与NECTAR引脚内反应速率测量的比较

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Tom Mager , Mathieu Hursin , Kyle Vaughn , Sooyoung Choi , Brendan Kochunas , Thomas Ligonnet , Vincent Lamirand , Oskari Pakari , Carlo Fiorina , Andreas Pautz
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引用次数: 0

摘要

高保真核反应堆仿真方法的发展对于降低反应堆安全裕度的保守性、优化反应堆设计和运行具有重要意义。本研究利用CROCUS反应堆的NECTAR实验数据,评估了确定性求解器GeN-Foam和MPACT在非均质反应堆堆芯中模拟针内反应速率分布的预测能力。GeN-Foam和MPACT的径向和方位反应速率分布与NECTAR测量结果进行了比较,并使用Serpent2蒙特卡罗模拟支持验证。GeN-Foam的预测结果与实验不确定度在0.4%以内的测量结果一致,而MPACT的结果需要进一步改进,以考虑实验的3D性质,特别是在模拟剂量计附近的轴向泄漏时;并在截面上对剂量学材料进行自屏蔽处理。为了支持更广泛的验证工作,本研究提供了NECTAR实验的详细描述,计划将其纳入国际反应堆物理评估项目(IRPhEP)。对未来的验证工作提出了建议,包括使用替代剂量计材料进行额外测量和改进求解方法。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Comparison of high-fidelity transport code predictions against the NECTAR intra-pin reaction rate measurements
The advancement of high-fidelity nuclear reactor simulation methods is essential for reducing conservatism in safety margins and optimizing reactor design and operation. This work evaluates the predictive capabilities of the deterministic solvers GeN-Foam and MPACT for modeling intra-pin reaction rate distributions in heterogeneous reactor cores, using experimental data from the NECTAR campaign conducted at the CROCUS reactor. Radial and azimuthal reaction rate distributions from GeN-Foam and MPACT are compared to NECTAR measurements, with Serpent2 Monte Carlo simulations supporting the validation. GeN-Foam predictions align with measurements within the 0.4% experimental uncertainty, while MPACT results require further improvements to account for the 3D nature of the experiments, particularly in modeling the axial leakage in the vicinity of the dosimeter; and in the cross-section self-shielding treatment of dosimetry materials. To support broader validation efforts, this study provides detailed descriptions of the NECTAR experiments, which are planned to be integrated into the International Reactor Physics Evaluation Project (IRPhEP). Recommendations are made for future validation efforts, including additional measurements with alternative dosimeter materials and enhancements to solver methodologies.
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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