核电站堆腔混凝土辐照试验研究  

Irradiation Experimental Research of Reactor Cavity Concrete in Nuclear Power Plant

作　　者：黄岗[1] 刘晓松[1] 李国云[1] 许怡幸 陈浩[1] 刘东彬 李延鹏 黄伟杰[1] 张平[1] 金帅 HUANG Gang;LIU Xiaosong;LI Guoyun;XU Yixing;CHEN Hao;LIU Dongbin;LI Yanpeng;HUANG Weijie;ZHANG Ping;JIN Shuai(Nuclear Power Institute of China,Chengdu 610213,China)

机构地区：[1]中国核动力研究设计院,四川成都610213

出　　处：《原子能科学技术》2024年第8期1725-1731,共7页Atomic Energy Science and Technology

基　　金：国家重点研发计划(2019YFB1900903)。

摘　　要：作为核电站关键材料的堆腔混凝土,其安全服役是核电站长期稳定安全运行的前提条件之一。为了进行堆腔混凝土的中子辐照损伤机理研究,获得堆腔混凝土在中子辐照环境下的试验数据,本文建立了堆腔混凝土辐照试验方法,研制了辐照试验装置,并在研究堆中对其进行了加速辐照试验。结果表明:辐照试验装置设计合理,辐照试验指标满足试验要求,实现了两种规格多个混凝土试样的中子辐照。进一步的混凝土试样辐照性能研究结果表明:混凝土试样在平均快中子注量3.41×10^(18) cm^(−2)下辐照后,与辐照前相比,其外部形状未见明显差异,但试样颜色变化较大,并且出现一定的辐照肿胀和力学性能退化现象。As a key material of nuclear power plant,the safe service of reactor cavity concrete is one of the prerequisites for the long-term stable and safe operation of nuclear power plant.In order to study the neutron irradiation damage mechanism of the reactor cavity concrete,obtain the test data of the reactor cavity concrete in the neutron irradiation environment,and provide a scientific basis for the long-term stable operation of the nuclear power unit,the irradiation test method of the reactor cavity concrete was established,and the irradiation test device with a water-passing basket structure was developed in this paper.The physical and thermal design of the irradiation test of the reactor cavity concrete was carried out with the numerical calculation method.The accelerated neutron irradiation test of the reactor cavity concrete was carried out in the 5#hole with a pressure tube in Minjiang Test Reactor(MJTR)by using the irradiation pile method with the reactor.The standard concrete samples of 50 mm×50 mm and the small concrete samples of 25 mm×25 mm were loaded in the cavity of the irradiation test section for the irradiation test device,and seven layers were arranged axially in the 1000 mm active area of the reactor.During the irradiation test,the pressure tube was filled with the deionized water,and the concrete sample was directly in contact with the deionized water.The neutron flux and the irradiation test temperature were measured by the neutron detector and the thermocouple respectively.The irradiation test results show that the irradiation test method is feasible,the irradiation test device is reasonable,and the neutron irradiation of multiple concrete standard samples and small samples is realized.The cumulative fast neutron flux of the concrete sample(E≥0.1 MeV)is distributed in 2.38×10^(18)-2.06×10^(18) cm^(−2),the temperature of the irradiation test is stable during 50-60℃,and the irradiation test index meets the test requirements.Furthermore,the appearance inspection,size measurement and ball

关 键 词：核电站 堆腔混凝土 中子辐照 辐照性能 试验研究 

分 类 号：TL341[核科学技术—核技术及应用]