Development of the ENIGMA fuel performance code for LWR applications with chromium-coated cladding

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2024-12-01 Epub Date: 2024-10-22 DOI:10.1016/j.nucengdes.2024.113656

Glyn Rossiter , Kerr Fitzgerald , Aiden Peakman

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Abstract

Zirconium-alloy cladding with a chromium coating is the most advanced of the near-term concepts amongst Accident Tolerant Fuel (ATF) materials for Light Water Reactor (LWR) applications. The ENIGMA fuel performance code has been updated to model the thermo-mechanical behaviour of such cladding in both normal and off-normal operating conditions. The focus was on accurately simulating the behaviour in Loss Of Coolant Accident (LOCA) conditions to evaluate the increase in coping time during design-basis accidents. New low-temperature and high-temperature models were incorporated for cladding oxidation and hydriding and cladding creep which take into account the impact of the chromium coating on the overall cladding behaviour. Furthermore, the consumption of the chromium coating due to high-temperature diffusion of chromium into the cladding base alloy’s β-Zr phase is simulated. The new models have been validated using measurements on chromium-coated cladding from irradiated rods, high-temperature annealing experiments and semi-integral LOCA tests. The validation showed good agreement between ENIGMA’s predictions and the experimental data; thereby demonstrating the applicability of the new models for simulating the performance of LWR fuel rods with chromium-coated cladding in both normal operation and accident conditions.

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为使用铬涂层包壳的轻水反应堆应用开发 ENIGMA 燃料性能代码

带铬涂层的锆合金包壳是轻水反应堆（LWR）近期应用的事故耐受燃料（ATF）材料中最先进的概念。ENIGMA 燃料性能代码已经更新，以模拟这种包层在正常和非正常运行条件下的热机械性能。重点是精确模拟失去冷却剂事故（LOCA）条件下的行为，以评估在设计基准事故期间应对时间的增加。针对堆芯氧化和水化以及堆芯蠕变，加入了新的低温和高温模型，其中考虑到了铬涂层对堆芯整体行为的影响。此外，还模拟了由于铬向包层基合金的 β-Zr 相高温扩散而导致的铬涂层消耗。通过对辐照棒铬涂层包层的测量、高温退火实验和半整合 LOCA 试验，对新模型进行了验证。验证结果表明，ENIGMA 的预测结果与实验数据非常吻合，从而证明了新模型适用于模拟带铬涂层的低温反应堆燃料棒在正常运行和事故条件下的性能。

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来源期刊

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.