Core-wide multi-physics simulation of fuel behaviour during large-break LOCA using NEXUS

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2025-02-12 DOI:10.1016/j.anucene.2025.111228
Aiden Peakman , Robert Gregg , Victor Martinez-Quiroga , Jordi Freixa
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Abstract

Large-break loss-of-coolant accidents (LB-LOCAs) are among the most critical scenarios in nuclear power plant safety analysis due to their potential to significantly challenge the integrity of barriers confining radioactive material. This study demonstrates, for the first time, the application of the NEXUS framework to perform detailed, core-wide fuel assessments during a design basis accident. NEXUS integrates RELAP for thermal-hydraulics, PARCS for neutronics and ENIGMA for fuel performance to analyse the thermo-mechanical responses of fuel rods across the reactor core during accident conditions. The analysis, applied to a 1240 MWe/3400 MWth Pressurised Water Reactor (PWR) with Optimized ZIRLO cladding and conventional UO2 fuel, presents a computationally efficient methodology to capture core-wide fuel behaviour — an area where comprehensive approaches remain scarce in the literature, particularly for metrics beyond peak cladding temperature.
An LB-LOCA scenario, specifically a double-ended guillotine break of a cold leg, was modelled as a design basis accident to evaluate fuel integrity under limiting conditions. Four LB-LOCA cases were simulated to assess the impact of varying power profiles and fuel states on cladding rupture stress and plastic hoop strain increment. Enhanced features in the ENIGMA code, including high-temperature clad creep, oxidation, and failure models, as well as a dynamic phase change model, were employed to facilitate margin-to-failure calculations under LOCA conditions. Results highlight relatively benign outcomes at the beginning of cycle (BOC) compared to more challenging end-of-cycle (EOC) scenarios, primarily driven by variations in rod internal pressures.
Both best-estimate and power conservatism cases were studied to assess fuel performance. The successful demonstration of NEXUS’ capabilities opens avenues for employing best-estimate plus uncertainty (BEPU) methodologies in future evaluations. Given its computational efficiency, this study highlights the NEXUS framework’s ability to balance detailed fuel assessments with reasonable computational demands for design basis accidents.
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利用 NEXUS 对大破裂 LOCA 期间的燃料行为进行全岩心多物理场模拟
冷却剂大断裂损失事故(LB-LOCAs)是核电站安全分析中最关键的情景之一,因为它们可能严重挑战限制放射性物质的屏障的完整性。本研究首次展示了NEXUS框架在设计基础事故中执行详细的全堆燃料评估的应用。NEXUS集成了用于热工水力学的RELAP、用于中子学的PARCS和用于燃料性能的ENIGMA,以分析事故条件下反应堆堆芯燃料棒的热机械响应。该分析应用于1240 MWe/3400 MWe压水堆(PWR),采用优化的ZIRLO包层和传统的UO2燃料,提出了一种计算效率高的方法来捕获堆芯范围内的燃料行为——这是一个文献中缺乏综合方法的领域,特别是对于超过峰值包层温度的指标。LB-LOCA场景,特别是冷腿的双端断头台断裂,作为设计基础事故建模,以评估限制条件下的燃料完整性。模拟了4种LB-LOCA情况,评估了不同功率分布和燃料状态对包层破裂应力和塑性环应变增量的影响。采用了ENIGMA代码中的增强功能,包括高温包层蠕变、氧化和失效模型,以及动态相变模型,以方便LOCA条件下的失效边际计算。结果显示,与更具挑战性的周期结束(EOC)情况相比,周期开始(BOC)的结果相对较好,主要是由抽油杆内部压力的变化驱动的。研究了最佳估计和功率保守性两种情况来评估燃油性能。NEXUS能力的成功演示为在未来的评估中采用最佳估计加不确定性(BEPU)方法开辟了道路。鉴于其计算效率,本研究强调了NEXUS框架平衡详细燃料评估与设计基础事故合理计算需求的能力。
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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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