PDF(973 KB)
铅基反应堆海洋核动力发展研究
吴宜灿, 柏云清, 李春京, 李阳, 刘少军, 王芳, 蒋洁琼, 吴庆生, 刘超, 周丹娜, 凤麟核团队
中国工程科学 ›› 2024, Vol. 26 ›› Issue (2) : 63-73.
PDF(973 KB)
PDF(973 KB)
铅基反应堆海洋核动力发展研究
Development of Lead-Based Reactor Marine Nuclear Power
铅基反应堆（铅基堆）核动力具有固有安全、小型轻量、长寿高效等突出优点，在先进海洋装备、无人潜航器、深海空间站的能源动力上应用前景广阔；在加快建设海洋强国的背景下，保障海洋能源供给成为重要的基础条件，开展铅基堆海洋核动力发展研究是推动我国海洋装备能源动力技术革新的关键内容。本文总结了海洋核动力的应用场景与发展需求，从技术特征、代表性应用、研制现状等方面系统梳理了铅基堆核动力的发展概况，凝练和剖析了包括核燃料与包壳材料、一回路关键设备、冷却剂工艺与氧测控、先进发电技术在内的铅基堆海洋核动力关键技术。立足国情研判了铅基堆海洋核动力面临的发展挑战，提出了低温铅基堆海洋核动力、高温高效铅基堆海洋核动力、一体化全自然循环铅基堆海洋核动力等可行技术路线。研究建议，强化前瞻性配套专项技术研发、加快部署装备示范工程，将铅基堆纳入重大能源战略、加快建设标准体系，设置国家级联合研发机构、构建科技创新和产业发展新模式，更好服务国家海洋战略并推动海洋核动力跨越式发展。
Lead-based reactor nuclear power has the advantages of inherent safety, compact size, light weight, long service life, and high efficiency, and it is widely applied to advanced marine equipment, unmanned underwater vehicles, and deep-sea space stations for energy and power purposes. Conducting research on lead-based reactor marine nuclear power is key to the technological innovation of energy and power for marine equipment in China. This study clarifies the application scenarios and development demands of marine nuclear power, summarizes the development status of lead-based reactor nuclear power from the aspects of technical characteristics, representative applications, and research status, and analyzes corresponding key technologies including nuclear fuel and cladding materials, key components in the primary loop, coolant processes and oxygen control, and advanced power generation technologies. Moreover, the study explores the development challenges for lead-based reactor marine nuclear power and proposes there feasible technical routes: low-temperature lead-based reactor marine nuclear power, high-temperature and high-efficiency lead-based reactor marine nuclear power, and integrated natural-circulation lead-based reactor marine nuclear power. Furthermore, we propose the following suggestions to promote the leapfrog development of marine nuclear power in China: (1) strengthening research and development (R&D) of specialized technologies for the lead-based reactor marine nuclear power and accelerating the deployment of demonstrative projects; (2) incorporating lead-based reactors into the country's major energy strategies and creating a standards system; (3) establishing national joint R&D centers and creating new models for technological innovation and industrial development.
铅基反应堆 / 海洋核动力 / 海洋装备 / 深海核电源 / 无人潜航器
lead-based reactor / marine nuclear power / marine equipment / deep-sea nuclear power station / unmanned underwater vehicle
| [1] |
卢川, 王仲辉, 于俊崇. 船用核动力的发展特点与启示 [J]. 核动力工程, 2022, 43(1): 1‒6.
Lu C, Wang Z H, Yu J C. Development characteristics and inspiration of marine nuclear power [J]. Nuclear Power Engineering, 2022, 43(1): 1‒6.
|
| [2] |
Lee K H, Kim M G, Lee J, et al. Recent advances in ocean nuclear power plants [J]. Energies, 2015, 8(10): 11470‒11492.
|
| [3] |
董海防. 海洋核动力平台发展研究综述 [J]. 船舶工程, 2019, 41(11): 5‒10.
Dong H F. Review on the marine nuclear power platform development [J]. Ship Engineering, 2019, 41(11): 5‒10.
|
| [4] |
郑洁, 余凡, 朱军民, 等. 海洋核动力装备国内外发展现况与前景展望 [J]. 中国工程科学, 2023, 25(3): 62‒73.
Zheng J, Yu F, Zhu J M, et al. Development status and prospect of marine nuclear power equipment in China and abroad [J]. Strategic Study of CAE, 2023, 25(3): 62‒73.
|
| [5] |
Ward S A. Forged in war: The naval-industrial complex and American submarine construction [J]. Defense AR Journal, 2015, 22: 35‒42.
|
| [6] |
Tsypin S G, Zhirnov, A D. Stages of physical investigations of the radiation shielding in the first nuclear submarine 'Leninskii Komsomol' [J]. Atomic Energy, 1996, 80(2): 111‒118.
|
| [7] |
Levy S. Sodium fast reactors (SFRs) and recyclers [C]. Anaheim: Advances in nuclear power plants, ICAPP 2008, 2008.
|
| [8] |
Gromov B F, Subbotin V I, Toshinsky G I. Application of lead-bismuth eutectic and lead melts as nuclear power plant coolant [J].Atomic Energy, 1992, 73: 1‒19.
|
| [9] |
李宗洋, 郭慧芳, 赵畅, 等. 国外铅铋堆发展及军事应用 [J]. 国外核新闻, 2020 (7): 29‒31.
Li Z Y, Guo H F, Zhao C, et al. Development and military application of lead-bismuth reactors abroad [J]. Foreign Nuclear News, 2020 (7): 29‒31.
|
| [10] |
伍赛特. 核动力装置应用于舰船推进领域的技术可行性分析及前景展望 [J]. 传动技术, 2023, 37(3): 45‒52.
Wu S T. Technical feasibility analysis and prospect of nuclear power plant used in the field of ship propulsion [J]. Drive System Technique, 2023, 37(3): 45‒52.
|
| [11] |
Jones G M. The development of nuclear propulsion in the royal navy, 1946—1975 [D]. Plymouth: University of Plymouth (Doctoral dissertation), 2019.
|
| [12] |
Chen X Z. A comparative analysis of Chinese and French nuclear motivations [J]. History of European Ideas, 1995, 20(1/2/3): 261‒269.
|
| [13] |
王琮, 于雷, 叶水生. 我国海上浮动核电站的核安全问题及建议 [J]. 科技导报, 2022, 40(4): 16‒22.
Wang C, Yu L, Ye S S. Nuclear safety issues and development proposals of floating nuclear power plant in China [J]. Science & Technology Review, 2022, 40(4): 16‒22.
|
| [14] |
吴秀霞. 加快推进深海装备技术体系化发展 [N]. 中国船舶报, 2023-03-10(02).
Wu X X. Accelerating the systematic development of deep-sea equipment technology [N]. China Ship News, 2023-03-10(02).
|
| [15] |
钟宏伟, 李国良, 宋林桦, 等. 国外大型无人水下航行器发展综述 [J]. 水下无人系统学报, 2018, 26(4): 273‒282.
Zhong H W, Li G L, Song L H, et al. Development of large displacement unmanned undersea vehicle in foreign countries: A review [J]. Journal of Unmanned Undersea Systems, 2018, 26(4): 273‒282.
|
| [16] |
吴天元, 江丽霞, 崔光磊. 水下观测和探测装备能源供给技术现状与发展趋势 [J]. 中国科学院院刊, 2022, 37(7): 898‒909.
Wu T Y, Jiang L X, Cui G L. Status and trends of energy power supply technologies for underwater equipment [J]. Bulletin of Chinese Academy of Sciences, 2022, 37(7): 898‒909.
|
| [17] |
苏更林. 第四代核能系统的六大候选堆型 [J].百科知识, 2022 (19): 24‒27.
Su G L. Six candidate reactor types for the fourth-generation nuclear energy system [J]. Encyclopedic Knowledge, 2022 (19): 24‒27.
|
| [18] |
吴宜灿, 王明煌, 黄群英, 等. 铅基反应堆研究现状与发展前景 [J]. 核科学与工程, 2015, 35(2): 213‒221.
Wu Y C, Wang M H, Huang Q Y, et al. Development status and prospects of lead-based reactors [J]. Nuclear Science and Engineering, 2015, 35(2): 213‒221.
|
| [19] |
Bandini G, Meloni P, Polidori M. Thermal-hydraulics analyses of ELSY lead fast reactor with open square core option [J]. Nuclear Engineering and Design, 2011, 241(4): 1165‒1171.
|
| [20] |
Nuclear Energy Agency. Accelerator-driven systems (ADS) and fast reactors (FR) in advanced nuclear fuel cycles: A comparative study [R]. Paris: Nuclear Energy Agency, 2002.
|
| [21] |
吴宜灿, 柏云清, 宋勇, 等. 中国铅基研究反应堆概念设计研究 [J]. 核科学与工程, 2014, 34(2): 201‒208.
Wu Y C, Bai Y Q, Song Y, et al. Conceptual design of China lead-based research reactor CLEAR-I [J]. Nuclear Science and Engineering, 2014, 34(2): 201‒208.
|
| [22] |
施征. 依然神秘的"阿尔法" [J]. 舰载武器, 2006 (9): 51‒54.
Shi Z. Mysterious Alfa class nuclear-powered attack submarine [J]. Shipborne Weapons, 2006 (9): 51‒54.
|
| [23] |
刘相春. 国外陆上模式堆建设情况及其对舰艇核动力装备发展的贡献分析 [J]. 中国舰船研究, 2015, 10(3): 84‒91.
Liu X C. Analysis of the construction instances of foreign land-based naval nuclear plant prototypes and the contribution to naval nuclear power equipment's development [J]. Chinese Journal of Ship Research, 2015, 10(3): 84‒91.
|
| [24] |
Zrodnikov A, Chitaykin V, Gromov B, et al. Use of Russian technology of ship reactors with lead-bismuth coolant in nuclear power [C]. Obninsk: Advisory Group Meeting on Small Power and Heat Generation Systems on the Basis of Propulsion and Innovative Reactor Technologies, 2000.
|
| [25] |
Kurata Y, Futakawa M, Saito S. Corrosion behavior of steels in liquid lead-bismuth with low oxygen concentrations [J]. Journal of Nuclear Materials, 2008, 373(1/2/3): 164‒178.
|
| [26] |
Stanculescu A. Worldwide status of advanced reactors (GEN IV) research and technology development [J]. Encyclopedia of Nuclear Energy, 2021: 478‒489.
|
| [27] |
Moiseev A V. Pilot demonstration reactor BREST-OD-300: Conceptual approaches and their implementation [R]. Vienna: International Atomic Energy Agency, 2021.
|
| [28] |
Adamov E O, Kaplienko A V, Orlor V V, et al. Brest lead-cooled fast reactor: From concept to technological implementation [J]. Atomic Energy, 2021, 129(4): 179‒187.
|
| [29] |
Castelluccio D M, Grasso G, Lodi F, et al. Nuclear data target accuracy requirements for advanced reactors: The ALFRED case [J]. Annals of Nuclear Energy, 2021, 162: 108533.
|
| [30] |
Chebac R, Cammi A, Ricotti M E, et al. ALFRED reactor and hybrid systems: A test case [J]. Annals of Nuclear Energy, 2023, 191: 109934.
|
| [31] |
Magni A, Bertolus M, Lainet M, et al. Fuel performance simulations of ESNII prototypes: Results on the MYRRHA case study [EB/OL]. (2022-01-01)[2024-04-10]. https://re.public.polimi.it/handle/11311/1227825.
|
| [32] |
Van Oost G, Terentyev D, Abderrahim H A. Contributions of MYRRHA to the European fusion energy roadmap [J]. Fusion Engineering and Design, 2024, 198: 114098.
|
| [33] |
Wallenius J, Qvist S, Mickus I, et al. Design of SEALER, a very small lead-cooled reactor for commercial power production in off-grid applications [J]. Nuclear Engineering and Design, 2018, 338: 23‒33.
|
| [34] |
Ghimire L, Waller E. Small modular reactors: Opportunities and challenges as emerging nuclear technologies for power production [J]. Journal of Nuclear Engineering and Radiation Science, 2023, 9(4): 044501.
|
| [35] |
Choi H, Bolin J, Gutierrez O, et al. Progress in fast modular reactor conceptual design [J/OL]. Nuclear Technology, [2024-04-10]. https://www.tandfonline.com/doi/full/10.1080/00295450.2024.2319925.
|
| [36] |
Wang J Y, Ke W. Development plan of unmanned system and development status of UUV technology in foreign countries [J]. Journal of Robotics and Control, 2022, 3(2): 187‒195.
|
| [37] |
Compton N A. The role of Russian submarines in Russian maritime strategy [D]. Monterey: Naval Postgraduate School (Master's thesis), 2021.
|
| [38] |
Warren A, Baxter P M. Nuclear modernization in the 21st Century [M]. London: Routledge, 2020.
|
| [39] |
Otsubo A, Takahashi M. Design study of PbBi- and NaK-cooled small deep sea fast reactors [J]. Progress in Nuclear Energy, 2005, 47: 202‒211.
|
| [40] |
Mun J, Kim H J, Ryu H J. Analysis of fuel performance under normal operation conditions of MicroURANUS: Micro long-life lead-bismuth-cooled fast reactor [J]. Frontiers in Energy Research, 2022, 10: 965319.
|
| [41] |
Wu Y C. Design and R & D progress of China lead-based reactor for ADS research facility [J]. Engineering, 2016, 2(1): 124‒131.
|
| [42] |
Wu Y C, Bai Y Q, Song Y, et al. Development strategy and conceptual design of China Lead-based Research Reactor [J]. Annals of Nuclear Energy, 2016, 87: 511‒516.
|
| [43] |
Jin M, Yang Q, Sa R Y, et al. Conceptual design of China lead-based mini-reactor CLEAR-M [C]. Obninsk: Fifth Conference on Heavy Liquid-Metal Coolants in Nuclear Technologies, 2018.
|
| [44] |
吴宜灿, 李亚洲, 金鸣, 等. 第五代核能系统概念及其特征 [J]. 核科学与工程, 2021, 41(2): 201‒210.
Wu Y C, Li Y Z, Jin M, et al. The concept and characteristics of the fifth generation nuclear energy system [J]. Nuclear Science and Engineering, 2021, 41(2): 201‒210.
|
| [45] |
Wang M J, Ju H R, Wu J, et al. A review of CFD studies on thermal hydraulic analysis of coolant flow through fuel rod bundles in nuclear reactor [J]. Progress in Nuclear Energy, 2024, 171: 105175.
|
| [46] |
Luo X, Teng Y F, Lu D G, et al. Comparative analysis on high-efficiency energy conversion system with different working mediums matched with small lead-cooled fast reactor [J]. Progress in Nuclear Energy, 2023, 164: 104844.
|
| [47] |
Zeng Y, Ming P J, Li F C, et al. Thermal hydraulic characteristics of spiral cross rod bundles in a lead-bismuth-cooled fast reactor [J]. Annals of Nuclear Energy, 2022, 167: 108850.
|
| [48] |
Heller J, Hatala B. D4.1 GFR refractory fuel qualification options [R]. Czechoslovakia: SafeG, 2022.
|
| [49] |
钱跃庆, 孙晓博, 刘文涛. 空间核反应堆电源用核燃料研制进展 [J]. 原子能科学技术, 2019, 53(1): 45‒49.
Qian Y Q, Sun X B, Liu W T. Development of nuclear fuel for space power reactor [J]. Atomic Energy Science and Technology, 2019, 53(1): 45‒49.
|
| [50] |
El-Alem M, Abdel-Latif A. The MOX fuel performance analysis of ALFRED core using MCNPX transport code [J]. Fayoum University Journal of Engineering, 2024, 7(2): 272‒277.
|
| [51] |
Feng K L, Li M F, Chen M Y, et al. Cyclic oxidation behavior of Al-Si coating on new γ'-strengthened cobalt-based superalloy: Experimental study and first-principles calculation [J]. Corrosion Science, 2021, 185: 109422.
|
| [52] |
Wang H, Xiao J, Wang H, et al. Corrosion behavior and surface treatment of cladding materials used in high-temperature lead-bismuth eutectic alloy: A review [J]. Coatings, 2021, 11(3): 364.
|
| [53] |
Agbevanu K T, Debrah S K, Arthur E M, et al. Liquid metal cooled fast reactor thermal hydraulic research development: A review [J]. Heliyon, 2023, 9(6): e16580.
|
| [54] |
Lim J, Manfredi G, Rosseel K, et al. Performance of electrochemical oxygen pump in a liquid lead-bismuth eutectic loop [J]. Journal of the Electrochemical Society, 2019, 166(6): 153‒158.
|
| [55] |
Toshinsky G I, Dedul A V, Komlev O G, et al. Lead-bismuth and lead as coolants for fast reactors [J]. World Journal of Nuclear Science and Technology, 2020, 10(2): 65‒75.
|
| [56] |
Liu Y P, Wang Y, Huang D G. Supercritical CO2 Brayton cycle: A state-of-the-art review [J]. Energy, 2019, 189: 115900.
|
| [57] |
邓清华, 胡乐豪, 李军, 等. 超临界二氧化碳发电技术现状及挑战 [J]. 热力透平, 2019, 48(3): 159‒165.
Deng Q H, Hu L H, Li J, et al. State-of-art and challenge on technologies of supercritical carbon dioxide electric power generation [J]. Thermal Turbine, 2019, 48(3): 159‒165.
|
| [58] |
Zare S, Tavakolpour-Saleh A R, Aghahosseini A, et al. Thermoacoustic stirling engines: A review [J]. International Journal of Green Energy, 2023, 20(1): 89‒111.
|
| [59] |
Gibson M A, Poston D I, McClure P R, et al. Heat transport and power conversion of the kilopower reactor test [J]. Nuclear Technology, 2020, 206: 31‒42.
|
/
| 〈 |
|
〉 |
