原子能科学技术2017，Vol.51Issue(12)：2288-2293,6.DOI:10.7538/yzk.2017.51.12.2288
棱柱式高温气冷空间核反应堆初步方案设计与中子物理分析
Preliminary Design and Neutronic Analysis of Prismatic High Temperature Gas-cooled Space Nuclear Reactor
杨谢 1佘顶 1石磊1
作者信息
- 1. 清华大学 核能与新能源技术研究院 ,先进核能技术协同创新中心 ,先进反应堆工程与安全教育部重点实验室,北京 100084
- 折叠
摘要
Abstract
Space power system based on fission nuclear reactor has advantages of large electric power ,high specific power and long-time running compared with solar energy and chemical fuel battery , and the space nuclear reactor is promising to be widely applied in space exploration .Based on high temperature gas-cooled reactor technology , a design case of space nuclear reactor power system was proposed ,where He-Xe mixture was adopted as the coolant of reactor and the working fluid of closed Brayton cycle .The designed space nuclear reactor is a small prismatic high temperature gas-cooled reactor employing the coated particle fuel ,and the thermal power is 5 MW .Monte Carlo meth-od was employed for neutronic analysis .The calculated results show that the designed reactor is capable of achieving 10 years of full power operation ,having negative reactivity temperature coefficient ,and remaining subcritical in submersion accident .关键词
空间核反应堆/包覆颗粒燃料/蒙特卡罗方法/中子物理分析Key words
space nuclear reactor/coated particle fuel/Monte Carlo method/neutronic analysis分类
能源科技引用本文复制引用
杨谢,佘顶,石磊..棱柱式高温气冷空间核反应堆初步方案设计与中子物理分析[J].原子能科学技术,2017,51(12):2288-2293,6.
