核电厂风冷散热器抗震分析与试验研究  

Seismic Analysis and Test for Air Cooler Radiator in a Nuclear Power Plant

作　　者：尤国英 张建栋 周钦 刘银芳 冯其 

机构地区：[1]中国船舶集团有限公司第七〇三研究所无锡分部,江苏 无锡 [2]中核霞浦核电有限公司,福建 宁德

出　　处：《核科学与技术》2023年第2期110-118,共9页Nuclear Science and Technology

摘　　要：风冷散热器是核电厂备用柴油发电机组配套的重要辅助设备之一,属于抗震I类设备,必须经过抗震鉴定。采用分析与试验组合法对某核电厂风冷散热器进行抗震鉴定。描述了风冷散热器抗震分析的力学模型、材料参数、载荷条件和计算结果,并依据RCC-M规范进行应力评定。介绍了风冷散热器进行抗震试验的样机设计、试验内容与要求和试验结果。对抗震试验结果和抗震计算结果进行了分析讨论,验证了计算分析模型和试验样机设计的合理性。鉴定结果表明,风冷散热器的抗震性能满足规范要求。采用的鉴定方法对核电厂大型设备的抗震鉴定有一定的借鉴意义。The air cooler radiator is an important auxiliary equipment of standby diesel-generator unit in a nuclear power plant. It is a seismic category I equipment and must be qualified. Seismic qualification was conducted on an air cooler radiator in a nuclear power plant by combining analysis with test. The mechanical model, materials parameters, load conditions and calculation results for seismic analysis were introduced, and structural stress was evaluated according to RCC-M standard. The design of test sample, test contents and requirements and test results for seismic experiments were introduced. The rationality of calculating model and design of test sample were verified by analysis of calculating results and seismic test results. Qualification results show that seismic performance of the air cooler radiator satisfies the requirements of relevant standards. Qualification methods have some reference significance for the seismic qualification of large-scale equipments in a nuclear power plant.

关 键 词：风冷散热器 抗震分析 有限元法 抗震试验 核电厂 

分 类 号：TU3[建筑科学—结构工程]