基于MCNP程序的海洋核动力平台堆芯核设计校核计算研究  

Nuclear Design Verification Calculation of Marine Nuclear Power Platform based on MCNP Code

作　　者：杨文 姚世卫[1] 邰云 邱金荣[1] 巢飞 李兴 Yang Wen;Yao Shiwei;Tai Yun;Qiu Jinrong;Chao Fei;Li Xing(Wuhan Second Ship Design and Research Institute,Wuhan 430064,China)

机构地区：[1]武汉第二船舶设计研究所,武汉430046

出　　处：《核安全》2022年第1期36-41,共6页Nuclear Safety

摘　　要：海洋核动力平台是小型核反应堆与船舶工程技术的有机结合,具有机动性好、一次性装料运行周期长、功率密度大、运行成本低、节能环保等特点。本文采用蒙特卡罗粒子输运程序(MCNP),建立海洋核动力平台反应堆堆芯几何模型,计算该反应堆首循环初始装料冷态、常压下的堆芯反应性和控制棒价值,并与核设计计算结果进行对比。结果表明:MCNP程序适用于海洋核动力平台反应堆堆芯核设计校核计算,并可与核设计值互相验证。The marine nuclear power platform is an organic combination of small nuclear reactor and ship engineering technology.It has the characteristics of good maneuverability,long on-time charging operation cycle,high power density,low operating cost,energy saving and environmental protection.In this paper,The core geometry model is built based on the design of the marine nuclear power platform reactor core.The core reactivity and control rod worth are calculated by a Monte Carlo code MCNP for this core design at first cycle,initial loading,normal temperature,and normal pressure condition.The results of the calculation are compared with nuclear design values.It shows that MCNP code is suitable for marine nuclear power platform core design calculation,and can be verified with nuclear design values.

关 键 词：海洋核动力平台 核设计 MCNP程序 反应性 控制棒价值 

分 类 号：TL329[核科学技术—核技术及应用]