文献类型：期刊文献

中文题名：示范快堆堆芯熔融物收集装置的安全分析

英文题名：Safety Analysis of Demonstration Fast Reactor Core Melt Collector

作者：刘兆阳[1];胡靖东[2];宫建国[2];曹健[3];高付海[1];轩福贞[2]

机构：[1]中国原子能科学研究院反应堆工程技术研究部,北京102413;[2]华东理工大学机械与动力工程学院,上海200237;[3]环境保护部核与辐射安全中心,北京100082

年份：2019

卷号：53

期号：8

起止页码：1445

中文期刊名：原子能科学技术

外文期刊名：Atomic Energy Science and Technology

收录：CSTPCD;;EI(收录号：20194607682118);Scopus;北大核心:【北大核心2017】；CSCD:【CSCD2019_2020】；

语种：中文

中文关键词：时间分数法;应变分数法;本构关系;蠕变强度

外文关键词：time fraction method;strain fraction method;constitutive relation;creep strength

摘要：针对示范快堆堆芯熔融物收集装置的高温结构完整性问题,采用堆芯熔融物滞留在反应堆压力容器策略有效性评估方法(IVR-DOE10460),建立了316H本构模型、多轴修正以及具体的分析评价方法。通过搜集与分析ASME规范和R66材料数据手册中316H钢相关的材料数据,确定了输入数据。在此基础上,利用有限元分析软件ABAQUS开展堆芯熔融物堆积形态下堆芯熔融物收集装置的应力应变分析,并基于时间分数法与延性耗竭法(应变分数法)对堆芯熔融物收集装置进行蠕变强度校核。有限元分析结果表明:堆芯熔融物收集装置在设计时间内可满足时间分数和应变分数小于1的蠕变强度考核要求,且满足竖直位移小于设计指标的功能性要求。堆芯熔融物收集装置在堆芯熔化严重事故后能保持结构的完整性。
For high temperature structural integrity question of the demonstration fast reactor core melt collector,strategy effectiveness valuation method(IVR-DOE10460)of core melt retention in reactor pressure vessel was adopted.The 316H constitutive model,multi axis correction and concrete evaluation method were established.By collecting the material data related to 316H steel in ASME code and R66 material data manual,the input data were determined.On this basis,the stress and strain analysis of the reactor core melt collector under the accumulation of core melts was carried out by using the finite element analysis software ABAQUS,and the creep strength of the reactor core melt collector was checked based on time fraction method and ductility exhaustion method(strain fraction method).The results of finite element analysis show that the core melt collector can meet the requirements of creep strength test with time fraction and strain fraction less than 1 within design lifetime and meet the functional requirement with a vertical displacement less than design target.The reactor core melt collector can maintain structural integrity after serious accident of core melts.