Zircaloy-4 fuel pin failure under simulated loss-of-coolant-accident conditions: Creep and rupture

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2024-08-01 DOI:10.1016/j.nucengdes.2024.113507

Saurabh Sagar , Mohd. Kaleem Khan , Manabendra Pathak , Suparna Banerjee , Tapan Kumar Sawarn , S.K. Yadav , R.N. Singh

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Abstract

This paper presents a detailed investigation of the creep and rupture behavior of Zircaloy-4 (Zry-4) fuel claddings used in Indian Pressurized Heavy Water Reactors (IPHWR) under simulated Loss-Of-Coolant Accident (LOCA) conditions. Fuel claddings are pre-oxidized in the steam environment at 500 °C to mimic the oxygen pickup during normal reactor operation. The burst tests are then performed on these preoxidized tubes at different heating rates (55–115 K/s) and internal overpressures (15–45 bar) in the steam environment, creating LOCA-like scenario in a high burnup condition, wherein the claddings further oxidize while undergoing deformation and rupture. The burst stress correlation is developed for IPHWR claddings from the obtained burst temperature and oxygen concentration data. A burst criterion model is developed by solving available creep rate, oxidation rate, and phase transformation equations simultaneously to study the effect of various parameters on burst characteristics of the fuel cladding. The proposed burst criterion model agrees well with the present and previous experimental burst data. Also, the ballooning progression predicted from the model is validated with the present and previous experimental data. In addition, the effect of available correlations for the creep rate, phase boundary temperature, and oxidation factor on the burst characteristics has been presented.

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Zircaloy-4 燃料销在模拟冷却塔失效事故条件下的失效：蠕变和断裂

本文详细研究了印度压水重水反应堆（IPHWR）使用的锆合金-4（Zry-4）燃料包壳在模拟冷却剂损失事故（LOCA）条件下的蠕变和破裂行为。燃料包壳在 500 °C 的蒸汽环境中进行预氧化，以模拟反应堆正常运行时的氧气拾取情况。然后在蒸汽环境中以不同的加热速率（55-115 K/s）和内部超压（15-45 巴）对这些预氧化管进行爆裂试验，在高燃耗条件下创造类似 LOCA 的情景，使包壳进一步氧化，同时发生变形和破裂。根据获得的爆裂温度和氧气浓度数据，为 IPHWR 包壳建立了爆裂应力相关性。通过同时求解可用的蠕变率、氧化率和相变方程，建立了爆裂标准模型，以研究各种参数对燃料包层爆裂特性的影响。所提出的爆裂标准模型与目前和以前的实验爆裂数据非常吻合。同时，模型预测的气球化进程也与目前和之前的实验数据进行了验证。此外，还介绍了蠕变速率、相边界温度和氧化因子的可用相关性对爆裂特性的影响。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.