摘要
                
                    利用JMCT程序模拟计算了压水堆内由核燃料裂变引起钴靶件的辐射释热率,包括裂变中子及其次级γ射线、裂变瞬发γ射线和裂变缓发γ射线的贡献,还计算了60 Co衰变产生的γ射线和β-射线引起钴靶件的辐射释热率。结果表明,在堆芯平均功率位置处,核燃料裂变所致的辐射释热率占总辐射释热率的84%,裂变瞬发γ射线和裂变缓发γ射线对总辐射释热率的贡献均为21%,60 Co衰变产生γ射线和β-射线所致的辐射释热率分别占总辐射释热率的12%和4%。在工程应用中,计算核燃料裂变引起的辐射释热率时还应考虑总功率峰因子F Q。
                
                A calculation model is established by using JMCT program to determine the heating rate induced by fission neutrons and their secondaryγ-ray,fission promptγ-ray,and fission delayedγ-ray in pressurized water reactor(PWR).Meanwhile,the heating rates caused by 60 Co decayγ-ray andβ-are also estimated.The results show that at the average core power position,the heating rate induced by the nuclear fuel fission accounts for 84%of the total heating rate.Both fission promptγ-ray and fission delayedγ-ray contribute 21%of the total heating rate.The 60 Co decayγ-ray andβ-contribute 12%and 4%of the total heating rate,respectively.For thermal safety analysis,the total power peak factor(F Q)should also be considered in calculating the radiation heating rate caused by nuclear fuel fission.
    
    
                作者
                    包鹏飞
                    苏耿华
                    谭世杰
                BAO Peng-fei;SU Geng-hua;TAN Shi-jie(China Nuclear Power Technology Research Institute,Shenzhen 518026,China;Daya Bay Nuclear Power Operations and Management Co.,Ltd.,Shenzhen 518124,China)
     
    
    
                出处
                
                    《现代应用物理》
                        
                        
                    
                        2020年第2期81-85,共5页
                    
                
                    Modern Applied Physics
     
    
                关键词
                    压水堆
                    钴靶件
                    辐射释热率
                    JMCT程序
                
                        pressurized water reactor
                        cobalt target
                        radiation heating rate
                        JMCT program
                
     
    
    
                作者简介
包鹏飞(1989-),男,江苏徐州人,工程师,硕士,主要从事反应堆屏蔽设计工作。E-mail:bao.pengfei@cgnpc.com.cn。