基于环形燃料的月球基地用长寿期核电源堆芯物理方案研究  

Study on Nuclear Design of Long-life Lunar Surface Nuclear Reactor Power Supply Based on Annular Fuel

作　　者：时运达 赵守智[1] 孙征[1] 胡彬和 袁晓明[2] 杨睿 SHI Yunda;ZHAO Shouzhi;SUN Zheng;HU Binhe;YUAN Xiaoming;YANG Rui(Department of Nuclear Engineering Design,China Institute of Atomic Energy,Beijing 102413,China;Department 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核工程设计研究所,北京102413 [2]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：《原子能科学技术》2025年第1期1-13,共13页Atomic Energy Science and Technology

基　　金：国家重点研发计划(2023YFB3506704)。

摘　　要：空间核反应堆电源具有结构紧凑、比功率大、寿命长、不依赖光照以及环境适应性强等优点,是月球基地最理想的能源解决方案。以美国FSP方案为参考,确定净输出电功率40 kW、寿期10 a为核电源的基本参数指标。对于月球基地用空间核反应堆电源,热中子反应堆方案相比快中子反应堆方案在减轻屏蔽体质量和节省核燃料方面更加具有竞争力。在对比分析了空间堆上几种常用的金属氢化物后,以长寿命为原则,选择YH_(1.8)作慢化剂。环形燃料作为一种革新性的燃料形式,具有双边慢化和双边冷却的特点,可以减小固体慢化剂的正温度效应并显著提高反应堆的热工安全裕量,是未来高性能反应堆的首选燃料形式。通过借鉴前苏联TOPAZ-Ⅱ空间堆的堆芯结构,在此基础上整合美国FSP方案的系统结构,最终设计出此堆芯方案。通过采用环形燃料元件并对栅格参数进行优化设计,解决了固体慢化剂带来的全堆正温度效应问题;通过引入安全棒设计,解决了特殊临界安全要求问题;通过采用YH_(1.8)慢化剂,解决了慢化剂的氢泄漏问题。以MCNP程序为计算工具,完成了.堆芯物理方案的设计与优化。与FSP方案相比,堆芯(含反射层)尺寸参数相当,没有因为使用慢化剂而使堆芯体积变大,并且^(235)U装量仅需18.463 kg,只有FSP方案的1/4。The space nuclear reactor power supply has the advantages of compact structure,high specific power,long service life,no dependence on light and strong environmental adaptability,making it the most ideal energy solution for lunar base.Taking the American FSP scheme as a reference,the ne output power of 40 kW and the life span of 10 years were determined as the basic parameters of the nuclear power supply.For the power supply of space nuclear reactor for lunar base,thermal neutron reactor scheme is more competitive than fast neutron reactor scheme in reducing shielding mass and saving nuclear fuel.After comparing and analyzing several commonly used metal hydrides in space reactors,YH_(1.8)is chosen as moderator based on the principle of long service life.As an innovative fuel form,annular fuel has the characteristics of bilateral moderating and bilateral cooling,which can reduce the positive temperature effect of solid moderator and significantly improve the thermal safety margin of the reactor.It is the preferred fuel form for high-performance reactors in the future.TOPAZ-Ⅱof the former Soviet Union is the most advanced type of space nuclear power supply that has been applied in engineering in the world at present,and its core physical scheme has a good reference significance.By referring to the core structure of TOPAZ-Ⅱspace reactor of the former Soviet Union and integrating the system structure of American FSP scheme,this core scheme was finally designed.By using annular fuel elements and optimizing lattice parameters,the problem of positive temperature effect of the whole reactor caused by solid moderator was solved.By introducing safety rod design,the problem of specia criticality safety requirements was solved.By using YH_(1.8)as moderator,the hydrogen leakage problem of moderator was solved.The MCNP program was used as the calculation tool to complete the design and optimization of the core physics scheme,and all indicators meet the design requirements of space reactor.Compared with the FSP scheme,it is

关 键 词：星表核电源 氢化钇 金属氢化物 固体慢化剂 反应性温度效应 低铀装量 特殊临界安全 

分 类 号：TL413[核科学技术—核技术及应用]