A novel viscoelastic creep model for zirconium alloy cladding under variable stress conditions

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

Annals of Nuclear Energy Pub Date : 2025-05-12 DOI:10.1016/j.anucene.2025.111551

Chengjie Wang, Xiaoyan Wei, Yani Liu, Yayun Luo, Xin Jin

引用次数: 0

Abstract

Creep deformation in zirconium alloy cladding is a critical concern for reactor safety and reliability. However, the strain hardening rule is experimentally known to fail to describe the creep strain of zirconium alloy cladding in scenarios such as load drop or reversal. This study introduces a novel viscoelastic creep model based on the Boltzmann superposition principle, addressing the limitations of traditional time and strain hardening models under variable stress conditions. Validated against Halden Reactor Project experiments (IFA-585, IFA-663, IFA-699, IFA-741), the model demonstrates reduced complexity and slightly improved accuracy compared to the Tulkki model. Key parameters were derived using a least squares fitting algorithm, showing excellent agreement with experimental data. This model enhances predictive capabilities for cladding creep, suggesting potential improvements for fuel behavior codes.

查看原文本刊更多论文

一种新的变应力条件下锆合金复层粘弹性蠕变模型

锆合金包层蠕变是影响反应堆安全性和可靠性的关键问题。然而，实验表明，应变硬化规律不能描述锆合金包层在载荷下降或逆转等情况下的蠕变应变。本文提出了一种基于玻尔兹曼叠加原理的粘弹性蠕变模型，解决了变应力条件下传统时间和应变硬化模型的局限性。通过Halden反应器项目实验（IFA-585, IFA-663, IFA-699, IFA-741）验证，与Tulkki模型相比，该模型的复杂性降低，精度略有提高。关键参数采用最小二乘拟合算法，与实验数据吻合良好。该模型增强了包层蠕变的预测能力，为燃料行为规范提出了潜在的改进建议。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

来源期刊

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.