核热火箭发动机反应堆结构特性分析  

Analysis on structural characteristics of nuclear thermal rocket reactor

作　　者：赵润喆 吕征[1] 解家春[1] 霍红磊 ZHAO Runzhe;LYU Zheng;XIE Jiachun;HUO Honglei(Research Institute of Reactor Engineering Technology,China Institute of Atomic Energy,Beijing 102413,China)

机构地区：[1]中国原子能科学研究院反应堆工程技术研究所,北京102413

出　　处：《火箭推进》2024年第4期31-41,共11页Journal of Rocket Propulsion

基　　金：核技术研发项目(HNKF202304(36));民用航天技术预先研究项目(D010102);原子能院院长基金项目(YZ222405000802)。

摘　　要：核热火箭具有推力大、比冲高的特点,在长距离、高载荷的空间任务中相较常规推进方式具有巨大优势。与地面常规反应堆相比,核热火箭反应堆尺寸、质量要求严格,同时运行温度高,热应力大,还需承受发射时的恶劣力学环境,因而需要合理稳固的结构设计。基于此需求开展调研总结,主要整理了美国NERVA-I型、NERVA-II型和CERMET燃料核热火箭反应堆的结构设计,梳理核热火箭反应堆典型结构设计,总结国外设计经验,为核热火箭方案迭代与实现提供参考。Nuclear thermal rockets have the advantages of large thrust and high specific impulse,offering significant advantages over conventional propulsion methods in long-distance and high-payload space missions.Compared with conventional ground-based reactors,nuclear thermal rocket reactors have strict requirements for size and weight,as well as high operating temperatures,significant thermal stress,and the need to withstand the harsh mechanical environment during launch.Therefore,a reasonable and stable structural design is necessary.Based on this requirement,a survey and summary of the structural design of the nuclear thermal rocket reactor is conducted in this acticle,mainly sorting out the structural design of NERVA-I,NERVA-II and CERMET fuel reactors in the United States.And then the foreign design experience is summarized and it provides reference for the iteration and implementation of nuclear thermal rocket program.

关 键 词：核热火箭 反应堆 结构 

分 类 号：TL99[核科学技术—核技术及应用] V439.5[航空宇航科学与技术—航空宇航推进理论与工程]