摘要
反应堆辐照材料上中子与γ的释热率是该材料在堆中热工计算的重要输入参数。本文基于蒙特卡罗粒子输运程序(MCNP),计算了某堆首炉高热中子堆芯布置下,L12中心孔道中不同材料(水、T6061铝、单晶硅、不锈钢、锆合金)轴向的中子、γ释热率分布。计算结果表明,活性区轴向高度为0~1000 mm,中子与γ在材料上的最大释热率点出现在310 mm处。不同材料上的中子与γ释热率分布不同,相较于中子,同一材料上的γ释热率更大,是材料发热的主要因素。
The heat release rate of neutrons and gamma on the irradiated material of the reactor is an important input parameter for the thermal calculation of the material in the reactor.Based on the Monte Carlo Particle Transport Program(MCNP),this paper calculates the distribution of neutron and gamma heat release rate of the axial direction of different materials(water,T6061 aluminum,single crystal silicon,stainless steel,zirconium alloy)in the L12 central channel under the core layout of a reactor first furnace high thermal neutron core.The calculation results show that,in the 0~1000 mm axial height of the active zone,the point of maximum heat release rate of neutron andγon the material appears at 310 mm.The distribution of neutrons and gamma heat release rates on different materials is different.Compared with neutrons,the gamma heat release rate on the same material is larger,which is the main factor of material heating.
作者
李敏
于成波
廖路
徐涛
高燊甫
孙世杰
刘旭东
Li Min;Yu Chengbo;Liao Lu;Xu Tao;Gao Shenfu;Sun Shijie;Liu Xudong(Nuclear Power Institute of China,Chengdu 610213,China)
出处
《核安全》
2022年第1期31-35,共5页
Nuclear Safety
关键词
MCNP
辐照材料
中子释热率
γ释热率
MCNP
irradiated material
neutron heat release rate
photon heat release rate
