PARCS pin-wise simulation with a cross section correction system based on the Super-Homogenisation method

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Kanglong Zhang, Luigi Mercatali, Victor Hugo Sanchez-Espinoza
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引用次数: 0

Abstract

A cross-section (XS) correction system was developed at the Karlsruhe Institute of Technology (KIT) for pin-wise simulations in PARCS, utilizing the SuPer-Homogenization (SPH) method in an iterative Python-based framework. The system uses Monte Carlo Serpent2 pin-wise solutions as a reference to correct homogenized pin-wise XS, improving PARCS’ accuracy in predicting neutron reaction rates and pin-wise power distributions. Verification was conducted with four test cases of increasing complexity: (a) a 3x3 mini assembly, (b) KONVOI reactor fuel assemblies, (c) a 3x3 mini-core, and (d) the Karlsruhe Small Modular Reactor (KSMR). Results show that the corrected XS significantly enhances PARCS’ diffusion solver accuracy, closely matching Serpent2 results, in pin-by-pin core simulations. Notably, this approach outperforms traditional assembly-wise Pin Power Reconstruction (PPR), particularly in central core regions. The key outcome of this work is that, for PARCS pin-wise simulations, computational accuracy is enhanced, making the prediction of local safety parameters feasible, especially if coupled with a Thermal-Hydraulic (TH) code, such as a sub-channel code. Furthermore, this work extends PARCS’s capability to perform pin-wise simulations with the standard nodal solver.
基于超均匀化方法的截面校正系统的PARCS引脚方向仿真
卡尔斯鲁厄理工学院(KIT)利用基于python的迭代框架中的超均匀化(SPH)方法,开发了一种用于PARCS引脚方向模拟的横截面(XS)校正系统。该系统使用蒙特卡罗Serpent2引脚方向解决方案作为参考,对均匀化的引脚方向XS进行校正,提高了PARCS预测中子反应速率和引脚方向功率分布的准确性。通过四个日益复杂的测试案例进行验证:(a) 3x3迷你组件,(b) KONVOI反应堆燃料组件,(c) 3x3迷你堆芯,以及(d)卡尔斯鲁厄小型模块化反应堆(KSMR)。结果表明,修正后的XS显著提高了PARCS扩散求解器的精度,与Serpent2在逐针核心模拟中的结果非常接近。值得注意的是,这种方法优于传统的组装式引脚功率重构(PPR),特别是在中央核心区域。这项工作的关键成果是,对于PARCS引脚模拟,计算精度得到了提高,使得局部安全参数的预测变得可行,特别是如果与热工(TH)代码(如子通道代码)相结合。此外,这项工作扩展了PARCS使用标准节点求解器执行引脚模拟的能力。
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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