在CAREM 25的启发下,利用GEANT4工具包估算复杂几何iPWR功率峰值因子的新方法

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-02-01 Epub Date: 2024-12-04 DOI:10.1016/j.nucengdes.2024.113729
Fatima Ghandour , Ziad Francis
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引用次数: 0

摘要

CAREM 25被认为是全球小型模块化反应堆(smr)的早期版本之一。尽管努力使用黑盒蒙特卡罗代码模拟CAREM,但本文是第一个使用开源软件(如GEANT4)模拟CAREM 25或任何其他具有完全复杂几何形状的堆芯反应堆。近年来的研究表明,GEANT4可以有效地分析核物理和工程中的中子输运。与之前的研究相比,本研究旨在说明GEANT4在评估CAREM反应器功率峰值因子(PPFs)方面的潜力。我们使用UserAction类和GEANT4中的内置ROOT工具包计算了燃料组件和燃料棒的功率峰值因子(ppf)。结果表明,功率分布趋于平缓,确保了功率密度最高的区域(PPF为1.502的中央燃料组件)与其他燃料组件之间的差距较小。这促进了稳定的反应堆行为,同时保持了安全边际。我们计算了108根燃料棒在最热组件和平均组件(PPF为1.005)中的详细PPF,揭示了燃料组件间的扁平功率分布。虽然由于条件的变化,无法实现对MCNPX的直接验证,但我们的调查发现了GEANT4和MCNPX的ppf的一致趋势,表明在燃料组件中具有相似的行为。这项研究为在具有复杂堆芯几何形状的反应堆物理中使用像GEANT4这样的开源代码迈出了重要的一步,需要进一步的研究来提高其有效性并与其他蒙特卡罗代码保持一致。
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A novel approach to estimate the power peaking factors in a complex geometry iPWR inspired by CAREM 25 using GEANT4 toolkit
CAREM 25 is considered one of the early versions of Small Modular Reactors (SMRs) worldwide. Despite efforts to simulate CAREM using black box Monte-Carlo codes, this paper is the first to simulate CAREM 25 or any other core reactor with full complex geometries using open-source software, such as GEANT4. Recent studies have demonstrated that GEANT4 can effectively analyze neutron transport in nuclear physics and engineering. This study aimed to illustrate the potential of GEANT4 in evaluating power peaking factors (PPFs) in the CAREM reactor compared to previous studies. We calculated the power peaking factors (PPFs) of the fuel assemblies and fuel rods using the UserAction classes and the built-in ROOT toolkit in GEANT4. The results showed a flattening of the power distribution, which ensures less disparity between regions with the highest power density (the central fuel assembly with a PPF of 1.502) and other fuel assemblies. This promotes stable reactor behavior while maintaining safety margins. We calculated the detailed PPFs of the 108 fuel rods in both the hottest assembly and the average assembly (with a PPF of 1.005), revealing a flattened power distribution across the fuel assemblies. While direct validation against MCNPX was not achievable due to variations in conditions, our investigation identified consistent trends in the PPFs of both GEANT4 and MCNPX, suggesting similar behavior across the fuel assemblies. This research takes an important step in employing open-source codes like GEANT4 in reactor physics with complex core geometries, with further investigations needed to enhance its effectiveness and alignment with other Monte Carlo codes.
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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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