Performance evaluation of accident tolerant Cr-coated Zr alloy cladding under accident conditions based on a refined degradation model

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Progress in Nuclear Energy Pub Date : 2024-07-19 DOI:10.1016/j.pnucene.2024.105359

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Abstract

A refined coating degradation model that comprehensively considers the phenomena of coating oxidation, diffusion, reduction, and volatilization is used to evaluate the performance of accident tolerant Cr-coated zirconium alloy cladding under accident conditions. The typical accident types of Station Blackout (SBO) and Large Break Loss of Coolant Accident (LBLOCA) are analyzed, with the consideration of three modes of coating failure: Failure in coating oxidation stage, Failure in oxide layer reduction stage, Failure caused by eutectic reaction. For the SBO accidents with relatively long time, the initial coating thickness of 9∼10 μm is recommended, which could provide good protection for zirconium alloy throughout the entire process and trigger the reduction of Cr₂O₃ before reaching Cr–Zr eutectic temperature to inhibit the occurrence of eutectic reaction. For the LBLOCA accidents where the cladding is rapidly heated, eutectic reaction is the dominant factor leading to coating failure, so how to avoid eutectic reaction failure remains to be further studied.

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基于细化降解模型的事故条件下耐受事故Cr涂层Zr合金包层的性能评估

该模型全面考虑了涂层氧化、扩散、还原和挥发等现象，用于评估事故条件下锆合金覆层的事故耐受性能。分析了典型的事故类型，如电站停电（SBO）和冷却剂大量泄漏事故（LBLOCA），并考虑了涂层失效的三种模式：涂层氧化阶段失效、氧化层还原阶段失效、共晶反应导致的失效。对于时间相对较长的 SBO 事故，建议初始涂层厚度为 9∼10 μm，这样可以在整个过程中为锆合金提供良好的保护，并在达到 Cr-Zr 共晶温度之前引发 Cr2O3 的还原，从而抑制共晶反应的发生。对于包壳快速加热的 LBLOCA 事故，共晶反应是导致涂层失效的主要因素，因此如何避免共晶反应失效仍有待进一步研究。

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来源期刊

Progress in Nuclear Energy 工程技术-核科学技术

CiteScore

5.30

自引率

14.80%

发文量

331

审稿时长

3.5 months

期刊介绍： Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.