先进核燃料用ZrC涂层材料的研究进展
Research Progress of ZrC Coating Materials for Advanced Nuclear Fuels
DOI: 10.12677/NST.2020.81005, PDF,  被引量    国家自然科学基金支持
作者: 李 刚, 王 辉, 吴松岭：中国核动力研究设计院反应堆燃料及材料重点实验室，四川 成都
关键词: ZrC涂层；ZrC-TRISO燃料；制备技术；高温稳定性；氧化行为；辐照性能；ZrC Coating； ZrC-TRISO Fuel； Preparation Technology； High Temperature Stability； Oxidation Behavior； Irradiation Performance
摘要: 先进高温/超高温反应堆对核燃料提出了更高的使用要求，ZrC涂层颗粒燃料具有优良的综合性能，是一种适用于高温反应堆的先进燃料。从ZrC涂层燃料的制备技术、高温稳定性、氧化行为、辐照性能等方概述了核燃料用ZrC涂层的研究现状，分析了在辐照环境下的ZrC涂层的氧化数据不全面，化学计量变化对辐照引起的膨胀、微观结构演变、辐照损伤以及与裂变产物的相容性等研究不系统，ZrC涂层在辐照及高温环境下的结构和机械稳定性缺乏广泛的辐照实验验证，ZrC涂层燃料与裂变产物的作用机制以及裂变产物在涂层中的分布、扩散规律缺乏充足认识等核燃料用ZrC材料的研究薄弱环节。
Abstract: Advanced high temperature/ultra-high temperature reactors have stringent application requirements for nuclear fuel. ZrC Coated particle fuel with excellent comprehensive performance is just an advanced fuel for high temperature reactor. The research status of ZrC coatings for nuclear fuel is summarized from the aspects of the preparation technology of ZrC coating, high temperature stability, oxidation behavior and irradiation performance. A series of scientific questions were proposed, including the incomplete oxidation data of ZrC coatings in irradiation environment, the effects of stoichiometry on swelling caused by irradiation, microstructure evolution, radiation damage and compatibility with fission products, the structure and mechanical stability of ZrC coatings under irradiation and high temperature environment are not verified by a lot of irradiation experiments, the mechanism of the interaction between fuel and fission products, the distribution and diffusion of fission products in the coatings are not fully understood.
文章引用：李刚, 王辉, 吴松岭. 先进核燃料用ZrC涂层材料的研究进展[J]. 核科学与技术, 2020, 8(1): 42-51. https://doi.org/10.12677/NST.2020.81005

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