Development and application of a mechanism-based fission gas release model in FROBA fuel performance code

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2026-05-01 Epub Date: 2025-12-26 DOI:10.1016/j.anucene.2025.112094

Kou Minghai , Xiao Xinkun , Yu Songjiao , Chen Ronghua , Jiang Pinting , Dai Mingliang , Zhang Kui , Wu Yingwei , Tian Wenxi , Qiu Suizheng

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引用次数: 0

Abstract

The release of fission gas in nuclear fuel significantly impacts fuel performance. Currently, many engineering models for fission gas release (FGR) rely on empirical corrections of simplified processes, introducing considerable uncertainty. Therefore, implementing mechanism-based FGR models grounded in physical behavior is crucial for improving the reliability of fuel performance codes. In this study, an established mechanism-based FGR model (incorporating atomic diffusion, intra-granular bubble re-solution, grain-boundary sweeping, and inter-granular bubble dynamics) was integrated into the fuel performance analysis code FROBA, along with a non-thermal release model. The implementation couples grain-boundary gas release with swelling equations. Model validation against literature benchmarks under steady-state conditions demonstrates excellent agreement with experimental data and other codes for both FGR fraction and swelling rate. Uncertainty analysis confirms the model’s effectiveness within the implemented scope.

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基于机理的裂变气体释放模型在FROBA燃料性能规范中的开发与应用

核燃料中裂变气体的释放严重影响核燃料的性能。目前，许多裂变气体释放（FGR）的工程模型依赖于简化过程的经验修正，引入了相当大的不确定性。因此，实现基于物理行为的FGR模型对于提高燃料性能代码的可靠性至关重要。在这项研究中，建立了一个基于机制的FGR模型（包括原子扩散、颗粒内气泡再溶解、晶界扫描和颗粒间气泡动力学），并将其与非热释放模型集成到燃料性能分析代码FROBA中。该实现将晶界气体释放与膨胀方程耦合。在稳态条件下对文献基准的模型验证表明，FGR分数和膨胀率与实验数据和其他代码非常吻合。不确定性分析证实了模型在实施范围内的有效性。

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

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.