Research progress in high-temperature thermo-mechanical behaviors for modelling Cr-coated cladding under loss-of-coolant accident condition

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Chunyu Yin , Guanghui Su , Libo Qian , Qingwen Xiong , Yu Liu , Yingwei Wu , Sijia Du , Jing Zhang , Zhong Xiao
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Abstract

Chromium (Cr)-coated zirconium cladding has emerged as a leading candidate for accident tolerant fuel (ATF) cladding in near-term engineering applications. This cladding demonstrates enhanced resistance to high-temperature oxidation, superior mechanical properties at elevated temperatures, and a relatively high level of technological maturity. Its performance under loss-of-coolant accident (LOCA) conditions is critical to reactor safety, making it a key focus of the present study. The present work introduces an overview of research progress on high temperature thermo-mechanical behaviors for Cr-coated cladding and provides a set of fundamental safety analysis models tailored for LOCA scenarios. First, essential models for LOCA safety analysis of Cr-coated cladding are identified, including a high-temperature oxidation model (along with a Cr coating consumption model), a high-temperature creep model, a high-temperature burst model, and an embrittlement criterion. Second, based on the evaluation of experimental data from high-temperature oxidation studies, models for the growth of Cr2O3 layer and oxygen absorption are recommended to estimate the oxidation rate of Cr-coated cladding. Additionally, a model for Cr coating consumption is proposed. Subsequently, through a comprehensive review and reevaluation of high-temperature creep and burst data, corresponding models for Cr-coated cladding are developed respectively. Finally, embrittlement data for Cr-coated cladding are analyzed, and embrittlement criteria for both one-sided oxidation and two-sided oxidation conditions are proposed.
失冷事故条件下cr包覆层高温热力学行为模拟研究进展
在近期工程应用中,铬(Cr)包覆锆包层已成为耐事故燃料(ATF)包层的主要候选材料。这种包层具有增强的抗高温氧化性,在高温下具有优越的机械性能,并且技术成熟度相对较高。它在失冷剂事故(LOCA)条件下的性能对反应堆安全至关重要,是目前研究的重点。本文介绍了cr包覆层高温热力学行为的研究进展,并提供了一套针对LOCA场景的基本安全分析模型。首先,确定了Cr包覆层LOCA安全分析的基本模型,包括高温氧化模型(以及Cr包覆层消耗模型)、高温蠕变模型、高温爆裂模型和脆化准则。其次,基于高温氧化实验数据的评估,推荐了Cr2O3层生长和氧吸收模型来估计cr包覆层的氧化速率。此外,还提出了Cr涂层消耗模型。随后,通过对高温蠕变和爆裂数据的全面回顾和重新评估,分别建立了相应的cr包覆层模型。最后,对cr包覆层的脆性数据进行了分析,提出了单侧氧化和双面氧化条件下的脆性判据。
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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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