Modelling FeCrAl cladding thermo-mechanical performance: CIEMAT’s contribution to IAEA/CRP ATF-TS

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-06-01 Epub Date: 2025-04-05 DOI:10.1016/j.nucengdes.2025.114034
Pau Aragón, Francisco Feria, Luis E. Herranz
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Abstract

This paper provides insights into the response of the advanced technology fuel (ATF) cladding FeCrAl during postulated design basis accident (DBA) and design extension condition without significant fuel degradation (DEC-A) scenarios. Such insights are gained through the development and application of in-house extensions of the FRAPCON/FRAPTRAN fuel performance codes, coupled with the statistical tool DAKOTA, within the framework of a loss-of-coolant accident (LOCA) safety evaluation methodology. While most of the specific FeCrAl models and correlations embedded in these extensions have been documented in the existing literature, the derivation of an instantaneous plasticity model describing the strain-hardening behaviour of FeCrAl alloy C26M is presented for the first time in this paper. The application of the methodology to the DEC-A/LOCA scenario suggests an improved performance of the advanced cladding material, as it maintains its integrity, in contrast to Zircaloy. However, in the DBA/LOCA scenario, no significant differences between these cladding materials were observed.
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模拟FeCrAl包层热力学性能:CIEMAT对IAEA/CRP ATF-TS的贡献
本文研究了先进技术燃料(ATF)包层FeCrAl在假定设计基础事故(DBA)和设计延伸条件下无显著燃料降解(deca)两种情况下的响应。这些见解是通过开发和应用内部扩展的FRAPCON/FRAPTRAN燃料性能代码,再加上统计工具DAKOTA,在冷却剂损失事故(LOCA)安全评估方法的框架内获得的。虽然这些扩展中嵌入的大多数特定FeCrAl模型和相关性已经在现有文献中得到了记录,但本文首次提出了描述FeCrAl合金C26M应变硬化行为的瞬时塑性模型的推导。将该方法应用于deca /LOCA方案表明,与锆合金相比,先进包层材料的性能得到了改善,因为它保持了完整性。然而,在DBA/LOCA方案中,没有观察到这些包层材料之间的显著差异。
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
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.
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