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1.南华大学 核科学技术学院 衡阳 421200
2.上海交通大学 核科学与工程学院 上海 200240
3.上海交通大学 智慧能源与创新学院 上海 200240
4.上海市数值反应堆技术融合创新中心 上海 200240
5.南华大学 资源环境与安全工程学院 衡阳 421200
朱鹏橙,男,2000年出生,南华大学本科在读,研究领域为先进核能系统设计
李卫,E-mail:cooLee@usc.edu.cn
收稿:2024-07-12,
修回:2024-12-21,
纸质出版:2025-11-15
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朱鹏橙,赵鹏程,刘晓晶等.核热推进反应堆多目标优化设计方法研究[J].核技术,2025,48(11):110601.
ZHU Pengcheng,ZHAO Pengcheng,LIU Xiaojing,et al.Multi-objective conceptual design method for nuclear thermal propulsion reactor[J].NUCLEAR TECHNIQUES,2025,48(11):110601.
朱鹏橙,赵鹏程,刘晓晶等.核热推进反应堆多目标优化设计方法研究[J].核技术,2025,48(11):110601. DOI: 10.3724/j.0253-3219.2025.hjs.48.240286. CSTR: 32193.14.hjs.CN31-1342/TL.2025.48.240286.
ZHU Pengcheng,ZHAO Pengcheng,LIU Xiaojing,et al.Multi-objective conceptual design method for nuclear thermal propulsion reactor[J].NUCLEAR TECHNIQUES,2025,48(11):110601. DOI: 10.3724/j.0253-3219.2025.hjs.48.240286. CSTR: 32193.14.hjs.CN31-1342/TL.2025.48.240286.
在深空探测任务对高性能推进系统的迫切需求下,针对现有核热推进反应堆(Nuclear Thermal Propulsion Reactor,NTPR)设计方法的系统性和完整性不足的问题,提出了一种NTPR多目标概念设计方法,以实现具有大推力、高比冲、长寿命和轻量化特点的NTPR堆芯设计。首先,该方法依据组件间的传热特点构建了组件间传热模型,并将其与核火箭的飞行性能及堆芯的临界状态相结合以便开展综合分析;其次,基于组件间传热模型、飞行性能模型以及组件二维临界模型,提出了一种多目标参数筛选方法,采用该方法对NTPR设计方案进行耦合迭代计算,以优化堆芯布局,确保满足热工、飞行和中子物理的综合设计标准,同时实现堆芯质量的最小化。在优化过程中,利用开源蒙特卡罗软件OpenMC对优化后的堆芯布局进行了详尽的三维中子学计算,这些计算针对反应堆的临界特性、安全特性以及燃耗表现等关键性能指标进行了全面评估。结果显示,基于该方法设计的低浓缩铀(Low-Enriched Uranium,LEU)NTPR概念设计方案初步满足了高性能设计要求,为未来载人深空探测任务提供了有价值的参考。
Background
2
The imperative need for high-performance propulsion systems in deep space exploration missions has led to a focus on improving the design of nuclear thermal propulsion reactor (NTPR). The existing methods for designing NTPRs have been identified as lacking in systematic and integral approaches.
Purpose
2
This study aims to propose a novel multi-objective optimization design method for NTPR to achieve a core design that offers high thrust
high specific impulse
extended service life
and reduced weight.
Methods
2
The methodology involved several key steps: constructing a heat transfer model between components based on their thermal interaction characteristics. This model was integrated with the flight performance model of the nuclear rocket and the two-dimensional criticality model of the components. A multi-objective parameter screening method was proposed that combined the aforementioned models for coupled iterative calculations to optimize the core layout. The design was ensured to meet comprehensive standards in thermal engineering
flight performance
and neutron physics while minimizing the core mass
with the specific impulse of 910 s
the thrust of 113 kN
the core mass of 2 645 kg
and the fuel temperature limit of 3 000 K. The open-source Monte Carlo software OpenMC was utilized to perform detailed three-dimensional neutronics calculations and conduct a comprehensive assessment of the reactor's criticality
safety
and burnup performance.
Results
2
The simulation results indicate that the Low-Enriched Uranium (LEU) NTPR conceptual design
developed using the proposed method
has a thrust of 110 kN
a specific impulse of 872 s
a maximum full-power operating time of over 7 h
and a dry core weight of approximately 2.63 t. This core design preliminarily meets the design criteria for high thrust
high specific impulse
long service life
and lightweight.
Conclusions
2
The results of this study suggest that the proposed method for NTPR core design is effective in meeting the demanding requirements of future manned deep space exploration missions
offering a promising direction for further research and development in this field.
洪刚 , 戚峰 , 王建明 , 等 . 载人登陆火星任务核热推进系统方案研究 [J ] . 载人航天 , 2018 , 24 ( 1 ): 102 – 106 . DOI: 10.16329/j.cnki.zrht.2018.01.017 http://dx.doi.org/10.16329/j.cnki.zrht.2018.01.017 .
HONG Gang , QI Feng , WANG Jianming , et al . Nuclear thermal propulsion system design for manned Mars mission [J ] . Manned Spaceflight , 2018 , 24 ( 1 ): 102 – 106 . DOI: 10.16329/j.cnki.zrht.2018.01.017 http://dx.doi.org/10.16329/j.cnki.zrht.2018.01.017 .
杨玉新 , 任全彬 , 段艳娟 , 等 . 美俄核热推进技术发展现状与启示 [J ] . 固体火箭技术 , 2023 , 46 ( 3 ): 399 – 409 .
YANG Yuxin , REN Quanbin , DUAN Yanjuan , et al . Development status and prospect of nuclear thermal propulsion technology in US and Russia [J ] . Journal of Solid Rocket Technology , 2023 , 46 ( 3 ): 399 – 409 .
吉宇 , 毛晨瑞 , 孙俊 , 等 . 核热火箭发动机系统循环方案分析与设计 [J ] . 火箭推进 , 2022 , 48 ( 1 ): 14 – 21 . DOI: 10.3969/j.issn.1672-9374.2022.01.002 http://dx.doi.org/10.3969/j.issn.1672-9374.2022.01.002 .
JI Yu , MAO Chenrui , SUN Jun , et al . Analysis and design of system cycle for nuclear thermal rocket engine [J ] . Journal of Rocket Propulsion , 2022 , 48 ( 1 ): 14 – 21 . DOI: 10.3969/j.issn.1672-9374.2022.01.002 http://dx.doi.org/10.3969/j.issn.1672-9374.2022.01.002 .
Nam S H , Venneri P , Kim Y , et al . Innovative concept for an ultra-small nuclear thermal rocket utilizing a new moderated reactor [J ] . Nuclear Engineering and Technology , 2015 , 47 ( 6 ): 678 – 699 . DOI: 10.1016/j.net.2015.06.003 http://dx.doi.org/10.1016/j.net.2015.06.003 .
Venneri P F , Kim Y . A feasibility study on low-enriched uranium fuel for nuclear thermal rockets–I: Reactivity potential [J ] . Progress in Nuclear Energy , 2015 , 83 : 406 – 418 . DOI: 10.1016/j.pnucene.2015.05.003 http://dx.doi.org/10.1016/j.pnucene.2015.05.003 .
Venneri P F , Kim Y . A feasibility study on low enriched uranium fuel for nuclear thermal rockets–II: Rocket and reactor performance [J ] . Progress in Nuclear Energy , 2016 , 87 : 156 – 167 . DOI: 10.1016/j.pnucene.2015.04.013 http://dx.doi.org/10.1016/j.pnucene.2015.04.013 .
Eades M , Deason W , Patel V . SCCTE: An LEU NTP concept with tungsten cermet fuel [J ] . Transactions of the American Nuclear Society , 2015 , 113 : 19 – 22 . DOI: 10.2172/1484269 http://dx.doi.org/10.2172/1484269 .
Runzhe Z , Honglei H . Preliminary study on neutronic characteristic of LEU NTR reactor SCCTE core [J ] . Atomic Energy Science and Technology , 2021 , 55 ( 2 ): 221 – 227 . DOI: 10.7538/yzk.2021. zhuankan.0239 http://dx.doi.org/10.7538/yzk.2021.zhuankan.0239 .
Nam S H , Venneri P , Kim Y , et al . Preliminary conceptual design of a new moderated reactor utilizing an LEU fuel for space nuclear thermal propulsion [J ] . Progress in Nuclear Energy , 2016 , 91 : 183 – 207 . DOI: 10.1016/j.pnucene.2016.02.008 http://dx.doi.org/10.1016/j.pnucene.2016.02.008 .
Krecicki M , Kotlyar D . Low enriched nuclear thermal propulsion neutronic, thermal hydraulic, and system design space analysis [J ] . Nuclear Engineering and Design , 2020 , 363 : 110605 . DOI: 10.1016/j.nucengdes. 2020.110605 http://dx.doi.org/10.1016/j.nucengdes.2020.110605 .
Zhang F T , Duan X , Zhang J , et al . Filtration performance and hydraulic characteristic analysis on the bottom nozzle in a fuel assembly of a nuclear energy system [J ] . Physics of Fluids , 2024 , 36 ( 12 ): 123359 . DOI: 10.1063/5.0238069 http://dx.doi.org/10.1063/5.0238069 .
Belair M L , Sarmiento C , Lavelle T . Nuclear thermal rocket simulation in NPSS [C ] // 49th AIAA/ASME/SAE/ASEE Joint Propulsion Conference . San Jose, CA. AIAA , 2013 : AIAA2013-4001. DOI: 10.2514/6.2013-4001 http://dx.doi.org/10.2514/6.2013-4001 .
Wang J C , Kotlyar D . High-resolution thermal analysis of nuclear thermal propulsion fuel element using OpenFOAM [J ] . Nuclear Engineering and Design , 2021 , 372 : 110957 . DOI: 10.1016/j.nucengdes.2020.110957 http://dx.doi.org/10.1016/j.nucengdes.2020.110957 .
Duan Z M , Zhang J , Wu Y W , et al . Multi-physics coupling analysis on neutronics, thermal hydraulic and mechanics characteristics of a nuclear thermal propulsion reactor [J ] . Nuclear Engineering and Design , 2022 , 399 : 112042 . DOI: 10.1016/j.nucengdes.2022.112042 http://dx.doi.org/10.1016/j.nucengdes.2022.112042 .
Labib S , King J . Design and analysis of a single stage to orbit nuclear thermal rocket reactor engine [J ] . Nuclear Engineering and Design , 2015 , 287 : 36 – 47 . DOI: 10.1016/j.nucengdes.2015.02.006 http://dx.doi.org/10.1016/j.nucengdes.2015.02.006 .
黄晓齐 . 第二类和第三类边界条件下非均匀内热源导热微分方程中的热流分流和叠加 [J ] . 贵州工学院学报(自然科学版) , 1996 , 25 ( 4 ): 37 – 42 .
HUANG Xiaoqi . Heat-flow distributing and superimposing in the heat-conduction differential equations of nonuniform internal heat-generation under the secondand third boundary conditions [J ] . Journal of Guizhou University of Technology (Natural Science Edition) , 1996 , 25 ( 4 ): 37 – 42 .
黄晓齐 , 龚德鸿 , 李环 . 非均匀内热源圆筒壁稳态导热微分方程的热流分流和叠加 [J ] . 贵州工业大学学报(自然科学版) , 2001 , 30 ( 3 ): 9 – 12 .
HUANG Xiaoqi , GONG Dehong , LI Huan . Heat-flow distribution and superimposing in steady heat-conduction differential equations of cylindrical wall with nonuniform generation [J ] . Journal of Guizhou University of Technology (Natural Science Edition) , 2001 , 30 ( 3 ): 9 – 12 .
李晓恒 , 陈金根 , 邹杨 , 等 . 燃料球体积填充率对2 MW先进高温堆物理特性的影响 [J ] . 核技术 , 2013 , 36 ( 6 ): 060604 . DOI: 10.11889/j.0253-3219.2013.hjs.36.060604 http://dx.doi.org/10.11889/j.0253-3219.2013.hjs.36.060604 .
LI Xiaoheng , CHEN Jingen , ZOU Yang , et al . Physical influence of spherical packing rate on the 2 MW AHTR [J ] . Nuclear Techniques , 2013 , 36 ( 6 ): 060604 . DOI: 10.11889/j.0253-3219.2013.hjs.36.060604. http://dx.doi.org/10.11889/j.0253-3219.2013.hjs.36.060604. .
李静 , 宋婧 , 龙鹏程 , 等 . 基于双向遍历的蒙特卡罗临界计算并行方法 [J ] . 核技术 , 2015 , 38 ( 6 ): 060602 . DOI: 10.11889/j.0253-3219.2015.hjs.38.060602 http://dx.doi.org/10.11889/j.0253-3219.2015.hjs.38.060602 .
LI Jing , SONG Jing , LONG Pengcheng , et al . Parallel computing method of Monte Carlo criticality calculation based on bi-directional traversal [J ] . Nuclear Techniques , 2015 , 38 ( 6 ): 060602 . DOI: 10.11889/j.0253-3219.2015.hjs.38.060602 http://dx.doi.org/10.11889/j.0253-3219.2015.hjs.38.060602 .
Sewell P H , Hayes R B . An assessment of heterogeneous effects on system reactivity for criticality safety analyses with LEU+ and HALEU materials [J ] . Nuclear Technology , 2023 , 209 ( 6 ): 835 – 856 . DOI: 10.1080/00295450.2022.2157662 http://dx.doi.org/10.1080/00295450.2022.2157662 .
沈芷睿 , 孙启政 , 何东豪 , 等 . 基于BEAVRS基准题高保真建模的OpenMC程序和NECP-X程序的对比验证 [J ] . 核技术 , 2022 , 45 ( 1 ): 010602 . DOI: 10.11889/j.0253-3219.2022.hjs.45.010602 http://dx.doi.org/10.11889/j.0253-3219.2022.hjs.45.010602 .
SHEN Zhirui , SUN Qizheng , HE Donghao , et al . Comparison and verification of NECP-X and OpenMC using high-fidelity BEAVRS benchmark models [J ] . Nuclear Techniques , 2022 , 45 ( 1 ): 010602 . DOI: 10.11889/j.0253-3219.2022.hjs.45.010602 http://dx.doi.org/10.11889/j.0253-3219.2022.hjs.45.010602 .
DeHart M D , Schunert S . Nuclear thermal propulsion [M ] // Nuclear Reactors . IntechOpen, 2022 . DOI: 10.5772/intechopen.103895 http://dx.doi.org/10.5772/intechopen.103895 .
程铭 , 吕征 , 贾玉文 . 基于3KEYMASTER平台的反应堆控制鼓特性仿真研究 [J ] . 核技术 , 2020 , 43 ( 6 ): 060007 . DOI: 10.11889/j.0253-3219.2020.hjs.43.060007 http://dx.doi.org/10.11889/j.0253-3219.2020.hjs.43.060007 .
CHENG Ming , LYU Zheng , JIA Yuwen . Simulation study on the characteristics of reactor control drum based on 3KEYMASTER platform [J ] . Nuclear Techniques , 2020 , 43 ( 6 ): 060007 . DOI: 10.11889/j.0253-3219.2020.hjs.43.060007 http://dx.doi.org/10.11889/j.0253-3219.2020.hjs.43.060007 .
刘黎丽 , 孙征 , 付子明 . SPACE-R意外掉落事故的临界安全分析 [J ] . 原子能科学技术 , 2015 , 49 ( 9 ): 1624 – 1628 .
LIU Lili , SUN Zheng , FU Ziming . Critical safety analysis of unexpected dropping accident for SPACE-R [J ] . Atomic Energy Science and Technology , 2015 , 49 ( 9 ): 1624 – 1628 .
Glushkov E S , Ponomarev-Stepnoi N N , Bubelev V G , et al . Water/sand flooded and immersed critical experiment and analysis performed in support of the TOPAZ-II safety program [C ] //Proceedings of the 12th Symposium on Space Nuclear Power and Propulsion: Conference on Alternative Power from Space; Conference on Accelerator-Driven Transmutation Technologies and Applications. Albuquerque , New Mexico (USA). AIP , 1995 : 539 – 542 . DOI: 10.1063/1.47144 http://dx.doi.org/10.1063/1.47144 .
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