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作 者:贾建英 马亮亮 丁志新 吴昊[3] 蓝晓明 JIA Jianying;MA Liangliang;DING Zhixin;WU Hao;LAN Xiaoming(State Key Laboratory of Nuclear Power Safety Monitoring Technology and Equipment,Shenzhen 518172,China;China Nuclear Power Engineering Co.,Ltd.,Shenzhen 518124,China;Department of Disaster Mitigation for Structures,Tongji University,Shanghai 200092,China)
机构地区:[1]核电安全监控技术与装备国家重点实验室,深圳518172 [2]中广核工程有限公司,深圳518124 [3]同济大学结构防灾减灾工程系,上海200092
出 处:《结构工程师》2025年第1期1-10,共10页Structural Engineers
基 金:国家自然科学基金面上项目(51878507)。
摘 要:针对核电堆坑潜在安全问题,采用数值模拟方法开展了蒸汽爆炸作用下反应堆厂房的完整性分析。首先,建立精细化反应堆厂房有限元模型,并得到板爆炸试验的验证。其次,根据损伤云图定性判断反应堆厂房结构的破坏范围。再次,通过位移和应变时程定量揭示反应堆厂房结构破坏机理,进一步根据拉应变云图并结合破坏阈值对安全壳的密封性能进行评估。最后,分析地基强度对于反应堆厂房结构抗蒸汽爆炸性能的影响,并给出核电厂房设计的建议。研究发现:蒸汽爆炸作用下堆坑侧壁完全破坏,且主要破坏模式是受拉破坏;堆坑底部2m深度范围内混凝土进入塑性,表现为剪切破坏;蒸汽爆炸作用下安全壳密封性保持完好。The integrity analysis of the reactor plant under steam explosion was numerically studied for the potential safety problem of the cavity.Firstly,a refined reactor plant finite element model(FEM)was established,and verified comprehensively based on a slab explosion test.Secondly,the damage scope of the reactor plant under steam explosion was determined qualitatively based on the damage contours.Then,the damage mechanism of the reactor plant was revealed based on the displacement-and strain-time histories quantitatively.Next,the tightness performance of the nuclear containment was analyzed according to the tensile strain contours and the damage threshold.Finally,the influence of foundation strength on the blast resistance of the reactor plant was analyzed and recommendations for the design of the nuclear power plant(NPP)were proposed.It derives that:under steam explosion,the cavity wall endures complete damage and the main damage mode is tensile failure.Besides,concrete at the cavity bottom within the depth of 2 m enters plastic state with shear failure;under steam explosion,the NPP containment is safe and the tightness of the containment is good.
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