NUCLEAR TECHNIQUES, Volume. 48, Issue 7, 070022(2025)
Design and analysis of a lunar nuclear reactor power core based on the TOPAZ-Ⅱ
Figures & Tables(17)
Fig. 1. Schematic representation of the TOPAZ-Ⅱ space reactor (a) and coolant circuit (b) (color online)
Fig. 2. Schematic representation of the SCTFE structure (color online)
Fig. 3. Schematic diagram illustrating the principle of SCTFE power generation (color online)
Fig. 4. Schematic diagram of the TOPAZ-Ⅱ space reactor core structure (color online)
Fig. 5. Schematic representation of the cross-section of the SCTFE and coolant channel (color online)
Fig. 6. The correlation between the keff and the moderator diameter (color online)
Fig. 8. The relationship between the keff and the thickness of the reflector
Fig. 9. Schematic representation of the fuel loading process of SCTFE (color online)
Fig. 10. Computational model of drop accident (a) and fuel loading method (b) (color online)
Fig. 11. Schematic diagram illustrating the deployment of the lunar reactor
Fig. 12. Distribution of the mean neutron fluence rate across the height of the core active zone (color online)(a) Thermal neutrons, (b) Epithermal neutrons, (c) Fast neutrons, (d) Total neutrons
Fig. 13. Axial distribution of the linear power density in the hottest channel (color online)
Table 1. Comparison of parameters for SCTFE and coolant channels prior to and following enhancement
View tableView in ArticleTable 1. Comparison of parameters for SCTFE and coolant channels prior to and following enhancement
参数Parameter 改进前Before improvement 改进后After improvement 变化幅度Change amount 发射极内半径 Emitter inner radius / cm 0.86 0.86 0 发射极外半径 Emitter outer radius / cm 0.965 1.06 0.095 发射极涂层外半径 Emitter coating outer radius / cm 0.98 1.075 0.095 接收极内半径 Collector inner radius / cm 1.03 1.125 0.095 接收极外半径 Collector outer radius / cm 1.17 1.265 0.095 接收极涂层外半径 Collector coating outer radius / cm 1.185 1.28 0.095 冷却剂内套管内半径 Coolant inner sleeve inner radius / cm 1.19 1.285 0.095 冷却剂内套管外半径 Coolant inner sleeve outer radius / cm 1.22 1.32 0.10 冷却剂外套管内半径 Coolant outer sleeve inner radius / cm 1.30 1.40 0.10 冷却剂外套管外半径 Coolant outer sleeve outer radius / cm 1.33 1.435 0.105 慢化剂开孔半径 Moderator opening radius / cm 1.37 1.475 0.105
Table 2. Comparison of scheme parameters
View tableView in ArticleTable 2. Comparison of scheme parameters
参数Parameter 原设计Original design 改进设计Improved design 参数变化幅度Change amount 发射极材料 Emitter material Mo-3Nb Mo-6Nb ― 发射极厚度 Emitter thickness / cm 0.105 0.200 0.095 冷却剂套管厚度 Coolant sleeve thickness / cm 0.030 0.035 0.005 慢化剂直径 Moderator diameter / cm 25.70 27.00 1.300 燃料活性区高度 Fuel height / cm 37.50 44.00 6.50 径向反射层厚度 Radial reflector thickness / cm 7.55 10.00 2.45 转鼓铍柱直径 Drum beryllium diameter / cm 6.70 9.00 2.30 燃料装量 Fuel loading / kg 22.87 26.84 3.97
Table 3. Core keff of the reactor under varying operational conditions
View tableView in ArticleTable 3. Core keff of the reactor under varying operational conditions
工况Condition 堆内是否进水Water-filled in reactor 堆外环境External environment keff±3σ（反应堆完整装料Fully fuel-loaded reactor） keff±3σ（堆芯第1圈3根元件不装料3 fuel elements missing in 1st ring） 1 是Yes 水Water 0.989 81±0.000 57 0.944 32±0.000 57 2 否No 干沙Dry sand 0.948 91±0.000 57 0.908 21±0.000 57 3 否No 湿沙W et sand 0.946 31±0.000 57 0.906 62±0.000 57 4 是Yes 湿沙W et sand 0.996 80±0.000 57 0.953 31±0.000 57
Table 4. Reactivity balance sheet
View tableView in ArticleTable 4. Reactivity balance sheet
平衡项Balance item 反应性效应 Reactivity effect / pcm 反应性效应Reactivity effects 燃耗效应Burnup effect -1 759 氢泄漏效应Hydrogen leakage effect -1 065 燃料轴向迁移效应Fuel axial migration effect -500 温度效应Temperature effect 1 547 寿期末最小后备反应性Minimum shutdown margin at end of life 500 待补偿的反应性Reactivity to be compensated 冷态Cold state 2 277 热态Hot state 3 824 停堆系统Ⅰ（卡1组鼓）价值Shutdown system I worth (1 drum jammed) 冷态Cold state 7 699 热态Hot state 8 260 停堆系统Ⅱ（卡住一组反射层）价值Shutdown system II worth (one reflector sector jammed) 冷态Cold state 5 150 热态Hot state 5 440
Tools
Get Citation
Copy Citation Text
Zheng WANG, Zheng SUN, Cheng HOU, Jing SHAO, Binhe HU, Jinduo WANG, Shouzhi ZHAO. Design and analysis of a lunar nuclear reactor power core based on the TOPAZ-Ⅱ[J]. NUCLEAR TECHNIQUES, 2025, 48(7): 070022
Paper Information
Category: Special Issue on The First Academic Annual Conference of the Research Reactor and Innovative Reactor Association of Chinese Nuclear Society and Advanced Nuclear Power System Reactor Engineering
Received: Feb. 13, 2025
Accepted: --
Published Online: Sep. 15, 2025
The Author Email: Zheng WANG (15765596320@163.com)
© Copyright 2018-2021 | Chinese Laser Press.
All Rights Reserved 沪ICP备15018463号-20