A failure criterion for nuclear fuel cladding due to internal gas

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-04-01 Epub Date: 2025-02-16 DOI:10.1016/j.nucengdes.2025.113909

Mingda Han , Hetong Liu , Weixu Zhang , Yibo Zhang , Songhui Luo

引用次数: 0

Abstract

The primary method for assessing cladding failure due to internal gas pressure involves comparing peak and ultimate pressures. When a small amount of gas is present, the pressure decreases as the volume expands at high temperatures, allowing the cladding to operate safely. This paper proposes a gas equilibrium-based failure criterion for cladding, determined by comparing the sectional force required by the gas with what the structure can provide. Finite element analysis compared cladding failure under three different boundary conditions (most used), using bidirectional fluid–structure interaction to investigate failure from internal gas. The critical load-bearing gas moles and the cross-sectional force changes with radial displacement for both hollow cladding and cladding with a fuel pellet were investigated. It was found that the critical gas quantity ratio is significantly smaller than the volume ratio, with gas pressure decreasing more rapidly in the pellet case.

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核燃料包壳内部气体失效判据

评估由内部气体压力引起的包层失效的主要方法包括比较峰值压力和极限压力。当有少量气体存在时，随着体积在高温下膨胀，压力会降低，从而使包层安全运行。本文提出了一种基于气体平衡的包层破坏准则，通过比较气体所需的截面力与结构所能提供的截面力来确定。有限元分析比较了三种不同边界条件下（最常用）的包层破坏，利用双向流固相互作用研究内部气体的破坏。研究了空心包壳和燃料球团包壳的临界承载气量和截面力随径向位移的变化规律。结果表明，临界气体量比明显小于体积比，且球团情况下气体压力下降更快。

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.