反应堆外围组件pin-by-pin压力容器屏蔽计算分析

Radiation Shielding Calculation of Pressure Vessel Based on Reactor Pin-by-pin Assembly

针对某三代压水堆,利用MCNP程序开展压力容器屏蔽计算。其中堆芯内部组件采用打混模型,外部组件采用pin-by-pin模型,组件建模采用MCNP重复结构卡进行描述,大大减少了建模工作量。计算给出了压力容器内壁周向和轴向快中子注量率分布情况。假设反应堆运行60 a,负荷因子为90%,计算得到快中子注量峰值,并将其与设计值进行比对。比对结果表明:计算值与设计值的相对偏差不大于5%,偏差在可接受的范围内。

Based on GEN-Ⅲ PWR power plant,shielding calculation of pressure vessel is calculated by using MCNP.The core internal assembly are mixed model;the external assembly are pin-by-pin model.The core assembly models use repetitive structure card of MCNP,greatly reducing the workload of modeling.Fast neutron flux distribution in pressure vessel wall is given along the circumferential and axial.Hypothesis reactor run 60 years,load factor is 90%,the fast neutron fluence peak value is calculated and compared with the design.It is shown that,the relative deviation between the calculated value and the design value is not greater than 5%,the deviation is in the acceptable range.