摘要
利用蒙特卡罗程序对采用合金法制备的Am-Be中子源辐照前中子源强能谱、伴生γ放射性等物理特性及其在堆内辐照过程中的变化情况进行了分析,评估了其作为压水型核电反应堆启动中子源的可行性。分析表明:合金法制作的单个Am-Be中子源(源活性区尺寸φ3.4 mm×236 mm,密度为4 g·cm^(-3))中子发射率可达3.34×10^(7)s^(-1),该源的源强虽低于核电厂反应堆常用的启动中子源,但多个Am-Be中子源叠加也可满足应用要求。Am-Be中子源在堆芯辐照过程中,由于产生的^(242)Cm等核素的影响,总中子源强高于其初始源强,保证其长期起到启动中子源作用。另外,Am-Be中子源具有较高的γ源强,在制造、运输与安装过程中需要考虑辐射防护问题。
In this paper,the Am-Be neutron source is produced by using the alloy method.Its physical characteristics,such as initial neutron source strength energy spectrum,associated gamma radioactivity,and their changes during irradiation in the reactor,are analyzed by Reactor Monte Carlo code(RMC)to assess its feasibility as startup neutron sources for pressurised water nuclear power reactors.The analysis shows that the neutron emission rate of single Am-Be neutron source(source active area size ofφ3.4 mm×236 mm,density of 4 g·cm^(-3))produced by using the alloy method can reach 3.34×10^(7) s^(-1).Although its source strength is lower than that of startup neutron sources commonly used in nuclear power plant reactors,the superposition of multiple Am-Be neutron sources can also meet the source strength requirements for reactor.During the core irradiation process,due to the production of 242 Cm and other nuclides,the total neutron source strength of Am-Be is higher than its initial neutron source strength,ensuring its long-term role as a startup neutron source.In addition,the Am-Be neutron source has a high gamma radioactivity,which requires consideration of radiation protection during manufacturing,transportation,and installation processes.
作者
王帅
吴师其
李满仓
周代杰
WANG Shuai;WU Shiqi;LI Mancang;ZHOU Daijie(Key Laboratory of Nuclear Reactor System Design Technology,Nuclear Power Institute of China,Chengdu 610213,China)
出处
《现代应用物理》
2024年第1期66-70,共5页
Modern Applied Physics
基金
国防科技工业核动力技术创新中心资助项目(HDLCXZX-2021-HD-011)。
