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混凝土中子辐照数值模拟研究综述

Review of numerical models of concretes under neutron irradiation
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摘要 安全高效发展核电是我国能源发展的战略方针。核电站堆腔混凝土的安全服役是核电站长期安全、高效运行的核心要素之一。我国在堆腔混凝土中子辐照领域研究起步晚,目前尚未建立系统、可靠、适用的堆腔混凝土服役行为评价体系,亟需开展相关研究。基于国内外最新进展,介绍了混凝土的中子辐照损伤机理,针对相关的数值模拟研究进展进行了汇总评述。指出目前混凝土中子辐照数值模拟在建模、模拟工具、模型验证方面均存在挑战,需在微观机制研究、辐照试验验证等方面开展进一步工作。 The safe and efficient development of nuclear power is the strategic policy of China′s energy development.The safety of nuclear reactor cavity concrete is one of the key elements of the long-term safe and efficient operation of nuclear power plants.The research in the field of reactor cavity concrete under neutron irradiation started late in our country.At present,a systematic,reliable and applicable evaluation system for the service behavior of reactor cavity concrete has not been established,and relevant research is urgently needed.Based on the latest developments reported in literature,the mechanism of concrete damage caused by neutron radiation is introduced,and the related numerical modeling progress is summarized and reviewed.It is pointed out that the current numerical models of concrete under neutron irradiation have challenges in modeling establishment,simulation tools,and model verification,and further work is needed in the aspects of research of mechanism in microscale and irradiation experiment verification.
作者 杨章灿 蓝欣昱 陈森 YANG Zhangcan;LAN Xinyu;CHEN Sen(Huazhong University of Science and Technology,Wuhan 430074,China;China Nuclear Power Operation Technology Corporation,Ltd.,Wuhan 430223,China)
出处 《混凝土》 CAS 北大核心 2023年第7期44-47,共4页 Concrete
基金 国家重点研发计划资助项目(2019YFB1900903)。
关键词 堆腔混凝土 核电站 中子辐照 数值模拟 reactor cavity concrete nuclear power plants neutron irradiation numerical modeling
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