A review of irradiation-induced hardening in FeCrAl alloy systems for accident-tolerant fuel cladding

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

Nuclear Engineering and Design Pub Date : 2024-10-22 DOI:10.1016/j.nucengdes.2024.113659

Abylay Tangirbergen , Nurlan Amangeldi , Shripad T. Revankar , Gani Yergaliuly

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Abstract

Despite nuclear energy being a clean, sustainable source, its safety is a major concern, especially after the Chernobyl and Fukushima accidents. Designing accident-tolerant fuel (ATF) clad materials is a key solution. This review examines the development and behavior of FeCrAl alloys, a promising ATF cladding candidate, under irradiation. FeCrAl alloys show excellent resistance to high-temperature corrosion and oxidation, but irradiation can significantly alter their mechanical properties. This paper consolidates experimental and theoretical studies on irradiation hardening in FeCrAl alloys, highlighting dislocation loops and Cr-rich α’ precipitates as primary hardening contributors. It discusses compositional adjustments, such as adding oxide dispersion strengthening (ODS) materials, and evaluates advanced techniques to mitigate irradiation-induced damage and improve alloy performance. Theoretical frameworks of irradiation hardening and computer simulation methods are overviewed. This review provides a comprehensive understanding of irradiation hardening mechanisms in FeCrAl alloys and suggests future research directions for enhancing nuclear reactor safety and efficiency.

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用于事故耐受燃料包壳的铁铬铝合金系统中的辐照诱导硬化综述

尽管核能是一种清洁、可持续的能源，但其安全问题却备受关注，尤其是在切尔诺贝利和福岛事故之后。设计事故耐受燃料（ATF）包层材料是一个关键的解决方案。本综述研究了铁铬铝合金（一种很有前途的 ATF 包层候选材料）在辐照下的发展和行为。铁铬铝合金具有优异的耐高温腐蚀和抗氧化性能，但辐照会显著改变其机械性能。本文综合了有关铁铬铝合金辐照硬化的实验和理论研究，强调位错环和富铬α'析出物是导致硬化的主要因素。报告讨论了成分调整，如添加氧化物分散强化（ODS）材料，并评估了减轻辐照诱发损伤和提高合金性能的先进技术。综述了辐照硬化的理论框架和计算机模拟方法。这篇综述提供了对铁铬铝合金辐照硬化机制的全面理解，并提出了提高核反应堆安全和效率的未来研究方向。

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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.