高温气冷堆新燃料元件运输容器临界安全分析  

Criticality Safety Calculation and Analysis of Fresh Fuel Element Transport Containers for High Temperature Gas-Cooled Reactor

作　　者：李颖虹 黄灏 周荣生 杨晓东 Li Yinghong;Huang Hao;Zhou Rongsheng;Yang Xiaodong(CGNPC Uranium Resources Co.Ltd.,Shenzhen,Guangdong,518000,China)

机构地区：[1]中广核铀业发展有限公司

出　　处：《核动力工程》2019年第6期64-71,共8页Nuclear Power Engineering

摘　　要：采用基于蒙特卡罗方法的MCNP5程序对高温气冷堆所用的球形燃料元件进行描述;根据包覆燃料颗粒在燃料球内的分布性质构建了8种不同模型,并研究不同模型对有效增殖因子(keff)和计算时间的影响,获得了临界计算问题中最优的燃料球模型;运用MCNP5描述燃料球运输容器,并研究了容器中子吸收板厚度、外容器壁厚、缓冲层材料、反射层材料、容器形状、容器结构缺失和水密度等影响运输容器临界安全的因素。结果表明,所研究的高温气冷堆新燃料元件运输容器在正常运输条件下和事故运输条件下均处于临界安全状态,其临界安全指数(CSI)可定为0。In this paper, the HTR-10 fuel pebbles were described by MCNP5 program which is based on the Monte Carlo method. Eight different fuel pebble models were constructed, and their keff values and computation time have been compared to obtain an optimal fuel pebble model. Then, using this optimal fuel pebble model, a HTGR fresh fuel elements transport container model was described by MCNP5. And a series of criticality influencing factors are calculated and analyzed, such as thickness of the neutron absorbing plate, wall thickness of the aluminum alloy tube, thickness of the outer container, buffer layer materials, reflector materials, deformation, structural loss, water submergence and infinite container arrays. The results showed that the HTGR fresh fuel elements transport container always remains in the criticality safety state, no matter under normal transportation conditions or under accidental transportation conditions. And its criticality safety index(CSI) can be set to zero.

关 键 词：高温气冷堆 燃料球 运输容器 MCNP 临界安全 

分 类 号：TL932.1[核科学技术—辐射防护及环境保护]