[1] Glanemann N, Willner S N, Levermann A. Paris climate agreement passes the cost-benefit test[J]. Nature Communications, 11, 110(2020).

[2] GU Baihe, YU Donghui, WANG Chen et al. Further considerations on the strategic transition pathways for deepening carbon peaking and carbon neutrality[J]. Bulletin of Chinese Academy of Sciences, 39, 726-736(2024).

[3] León S B. World nuclear performance Report 2024[R](2024).

[4] Kelly J E. Generation IV International Forum: a decade of progress through international cooperation[J]. Progress in Nuclear Energy, 77, 240-246(2014).

[5] ZHAO Xiaoze, LIU Bo, ZHANG Pingxun. Overview of the development of Generation IV nuclear energy systems under the carbon peaking and carbon neutrality goals[J]. Nuclear Science and Technology, 12, 204(2024).

[6] LI Kaixuan, ZHANG Zixiong, WEI Qianglin et al. Effects and analysis of different coolants on core physical parameters of lead-cooled fast reactors[J]. Science Technology and Engineering, 24, 12152-12158(2024).

[7] Agency IAE. Status of fast reactor research and technology development[R](2013).

[8] WU Yican, WANG Minghuang, HUANG Qunying et al. Current status of research and development prospects of lead-based reactors[J]. Nuclear Science and Engineering, 35, 213-221(2015).

[9] Choi S, Hwang I S, Cho J H et al. URANUS: Korean lead-bismuth cooled small modular fast reactor activities[C], 107-112(2012).

[10] Pyeon C H. Accelerator-driven system (ADS) study in Kyoto University research reactor institute (KURRI)[M]. Nuclear Back-end and Transmutation Technology for Waste Disposal, 81-91(2014).

[11] Wu Y C. Design and R&D progress of China lead-based reactor for ADS research facility[J]. Engineering, 2, 124-131(2016).

[12] ZHENG Jie, YU Fan, ZHU Junmin et al. Current status and prospects of domestic and international development of marine nuclear power equipment[J]. Engineering Sciences, 25, 62-73(2023).

[13] ZHAN Wenlong, YANG Lei, YAN Xuesong et al. Research progress of accelerator-driven advanced nuclear energy systems[J]. Atomic Energy Science and Technology, 53, 1809-1815(2019).

[14] WANG Jianqiang, DAI Zhimin, XU Hongjie. Current research status and prospects of comprehensive utilization of nuclear energy[J]. Bulletin of Chinese Academy of Sciences, 34, 460-468(2019).

[15] WU Yican, BAI Yunqing, LI Chunjiang et al. Development research on marine nuclear power based on lead-cooled reactors[J]. Engineering Sciences, 26, 63-73(2024).

[16] Alemberti A, Smirnov V, Smith C F et al. Overview of lead-cooled fast reactor activities[J]. Progress in Nuclear Energy, 77, 300-307(2014).

[17] Waltar A E, Todd D R, Tsvetkov P V[M]. Fast spectrum reactors(2012).

[18] Glazov A G, Leonov V N, Orlov V V et al. Brest reactor and plant-site nuclear fuel cycle[J]. Atomic Energy, 103, 501-508(2007).

[19] Zrodnikov A V, Toshinsky G I, Komlev O G et al. SVBR-100 module-type fast reactor of the IV generation for regional power industry[J]. Journal of Nuclear Materials, 415, 237-244(2011).

[20] Adamov E O, Kaplienko A V, Orlov V V et al. Brest lead-cooled fast reactor: from concept to technological implementation[J]. Atomic Energy, 129, 179-187(2021).

[21] Orlov A I, Gabaraev B A. Heavy liquid metal cooled fast reactors: peculiarities and development status of the major projects[J]. Nuclear Energy and Technology, 9, 1-18(2023).

[22] Valery R. Fast reactor development program in Russia[C](2013).

[23] Toshinsky G, Petrochenko V. Modular lead-bismuth fast reactors in nuclear power[J]. Sustainability, 4, 2293-2316(2012).

[24] Zrodnikov A V, Toshinskii G I, Grigor'ev O G et al. SVBR-75/100 multipurpose modular low-power fast reactor with lead–bismuth coolant[J]. Atomic Energy, 97, 528-533(2004).

[25] Zrodnikov A V, Toshinsky G I, Komlev O G et al. Innovative nuclear technology based on modular multi-purpose lead–bismuth cooled fast reactors[J]. Progress in Nuclear Energy, 50, 170-178(2008).

[26] Short M P, Ballinger R G. A functionally graded composite for service in high-temperature lead- and lead-bismuth–cooled nuclear reactors: I: design[J]. Nuclear Technology, 177, 366-381(2012).

[27] Smith C F, Halsey W G, Brown N W. SSTAR: The US lead-cooled fast reactor (LFR)[J]. Journal of Nuclear Materials, 376, 255-259(2008).

[28] Cinotti L, Smith C F, Sekimoto H. Lead-cooled fast reactor (LFR) overview and perspectives[C](2009).

[29] Sienicki J J, Moisseytsev A, Bortot S et al. SUPERSTAR: an improved natural circulation, lead-cooled, small modular fast reactor for international deployment[C], 2-5(2011).

[30] Bortot S, Moisseytsev A, Sienicki J J et al. Core design investigation for a SUPERSTAR small modular lead-cooled fast reactor demonstrator[J]. Nuclear Engineering and Design, 241, 3021-3031(2011).

[31] Alemberti A, Tuček K, Obara T et al. Status of Generation-IV Lead Fast Reactor Activities[C](2017).

[32] Greenspan E, Hong S G, Lee K B et al. Innovations in the ENHS reactor design and fuel cycle[J]. Progress in Nuclear Energy, 50, 129-139(2008).

[33] Wu Y, Bai Y, Wang W et al. Overview of PbBi-cooled reactor development and ADS program in China[C](2011).

[34] ZHAN Wenlong, XU Hushan. Advanced fission energy program-ADS transmutation system[J]. Bulletin of Chinese Academy of Sciences, 27, 375-381(2012).

[35] XIAO Guoqing, XU Hushan, WANG Sicheng. HIAF and CiADS national research facilities: progress and prospect[J]. Nuclear Physics Review, 34, 275-283(2017).

[36] Yu R, Gu L, Sheng X et al. Review of fuel assembly design in lead-based fast reactors and research progress in fuel assembly of China initiative accelerator driven system[J]. International Journal of Energy Research, 45, 11552-11563(2021).

[37] XU Hushan, ZHAN Wenlong, XIAO Guoqing et al. Progress and prospects of the national major scientific and technological infrastructure HIAF and CiADS construction[J]. Atomic Nuclear Physics Reviews, 41, 60-66(2024).

[38] Stanisz P, Oettingen M, Cetnar J. Monte Carlo modeling of lead-cooled fast reactor in adiabatic equilibrium state[J]. Nuclear Engineering and Design, 301, 341-352(2016).

[39] Locatelli G, Mancini M, Todeschini N. Generation IV nuclear reactors: current status and future prospects[J]. Energy Policy, 61, 1503-1520(2013).

[40] Cinotti L, Smith C F, Sienicki J J et al. The potential of the LFR and the ELSY project[J]. Revue Générale Nucléaire, 2007, 30-39.

[41] Grasso G, Petrovich C, Mattioli D et al. The core design of ALFRED, a demonstrator for the European lead-cooled reactors[J]. Nuclear Engineering and Design, 278, 287-301(2014).

[42] Alemberti A, Mansani L, Frogheri M. The ELFR industrial plant and ALFRED demonstrator[C](2013).

[43] Zhang Y, Wang C L, Lan Z K et al. Review of thermal-hydraulic issues and studies of lead-based fast reactors[J]. Renewable and Sustainable Energy Reviews, 120, 109625(2020).

[44] Wallenius J, Qvist S, Mickus I et al. SEALER: A small lead-cooled reactor for power production in the Canadian Arctic[C](2017).

[45] 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, 338, 23-33(2018).

[46] Dehlin F, Wallenius J. Activation analysis of the lead coolant in SUNRISE-LFR[J]. Nuclear Engineering and Design, 414, 112503(2023).

[47] He Y, Wang Z, Qin Z et al. Development of accelerator driven advanced nuclear energy (ADANES) and nuclear fuel recycle[C](2019).

[48] Maes D. Mechanical design of the small-scale experimental ADS: MYRRHA[J]. Energy Conversion and Management, 47, 2710-2723(2006).

[49] Takahashi M, Uchida S, Kasahara Y. Design study on reactor structure of Pb–Bi-cooled direct contact boiling water fast reactor (PBWFR)[J]. Progress in Nuclear Energy, 50, 197-205(2008).

[50] Nakazima T, Rivai A K, Hata K et al. Study plan for material corrosion test in lead and bismuth eutectic at high temperature[C], 627-629(2008).

[51] Yan M Y, Sekimoto H. Design research of small long life CANDLE fast reactor[J]. Annals of Nuclear Energy, 35, 18-36(2008).

[52] Margulis M. Zero power reactors in support of current and future nuclear power systems[J]. Nuclear Engineering and Design, 425, 113330(2024).

[53] YU Qingyuan, XIAO Hao, LIU Zijing et al. A coolant suitable for small long life natural circulation lead-based fast reactor[J]. Nuclear Techniques, 45, 030601(2022).

[54] Choi S, Cho J H, Bae M H et al. PASCAR: Long burning small modular reactor based on natural circulation[J]. Nuclear Engineering and Design, 241, 1486-1499(2011).

[55] Nguyen T D C, Khandaq M F, Jeong E et al. MicroURANUS: Core design for long-cycle lead-bismuth-cooled fast reactor for marine applications[J]. International Journal of Energy Research, 45, 12426-12448(2021).

[56] LI Xiang, XIAO Huiwen, LIU Guoming et al. Core optimization design of lead-cooled fast reactor based on SARAX Program[J]. Nuclear Science and Engineering, 43, 721-726(2023).

[57] ZHU Qingfu, ZHOU Qi, XIA Zhaodong et al. First physical start-up of the core of the lead reactor in the Venus II zero power facility[J]. Atomic Energy Science and Technology, 55, 577-583(2021).

[58] FANG Haitao, ZHAO Yongsong, ZHANG Xilin et al. Design of the fuel management scheme for the core of the lead-cooled fast reactor M2LFR-1000[J]. High Power Laser and Particle Beams, 30, 096003(2018).

[59] CHENG Songbai, CHEN Xiaolin, CHENG Hui[M]. Fundamentals of thermal hydraulic and safety analysis of liquid metal cooled reactor(2022).

[60] CHENG Songbai, ZHOU Wenzhong, GUO Jingyu et al[M]. Fundamentals of fuels and materials for liquid metal cooled reactor(2024).

[61] Guo H J, Li W, Zhang J et al. Analysis of flow-induced vibration of wire-wrapped fuel assemblies under the liquid metal axial flow in the Gen-IV nuclear reactor[J]. Annals of Nuclear Energy, 188, 109811(2023).

[62] Zhukov V A, Kuzina Y A, Sorokin A P. An experimental study of heat transfer in the core of a BREST-OD-300 reactor with lead cooling on models[J]. Thermal Engineering, 49, 175-184(2002).

[63] Jaeger W. Empirical models for liquid metal heat transfer in the entrance region of tubes and rod bundles[J]. Heat and Mass Transfer, 53, 1667-1684(2017).

[64] Fomichev D V, Solonin V I. A CFD analysis of hydraulic characteristics of the rod bundles in the BREST-OD-300 wire-spaced fuel assemblies[C], 8, 1514-1519(2014).

[65] Zhang J, Wang Y J, Qiu H R et al. Large eddy simulation on the lead-bismuth eutectic jet at reactor core outlet[J]. Applied Thermal Engineering, 258, 124581(2025).

[66] ZHANG Yifan, LIU Zhouyu, CAO Liangzhi et al. Transient safety analysis of small lead-bismuth cooled fast reactor[J]. Atomic Energy Science and Technology, 54, 8(2020).

[67] Tarantino M, Angiolini M, Bassini S et al. Overview on lead-cooled fast reactor design and related technologies development in ENEA[J]. Energies, 14, 5157(2021).

[68] Wang G. A review of recent numerical and experimental research progress on CDA safety analysis of LBE-/ lead-cooled fast reactors[J]. Annals of Nuclear Energy, 110, 1139-1147(2017).

[69] Wang Z, Wang G, Gu Z X et al. Preliminary simulation of fuel dispersion in a Lead-Bismuth Eutectic (LBE)-cooled research reactor[J]. Progress in Nuclear Energy, 85, 337-343(2015).

[70] LIU Dongxiang, LU Li. Analysis of the effect of different temperatures of LBE on the vibration characteristics of the main container[J]. Journal of Sichuan University of Science and Engineering (Natural Science Edition), 37, 27-33(2024).

[71] Hu Y, Liang L, Chen L et al. A model predictive controller for the core power control system of a lead-cooled fast reactor[J]. Frontiers in Energy Research, 10, 893528(2022).

[72] Yang M H. Axial power distribution control in fast nuclear reactor based on proportional spatial-derivative method[J]. Annals of Nuclear Energy, 150, 107800(2021).

[73] WU Guowei. Design and research on passive waste heat removal system of lead-based reactor[D](2017).

[74] Liang R X, Zhu H P, Sheng Z H et al. Experimental studies on active oxygen control performance of solid PbO mass exchanger in liquid lead–bismuth eutectic loop[J]. Annals of Nuclear Energy, 192, 109977(2023).

[75] Li X B, Liang R X, Wang Y F et al. An optimized numerical method on corrosion in the non–isothermal lead–bismuth eutectic loops with solid–phase oxygen control system[J]. Annals of Nuclear Energy, 172, 109084(2022).

[76] Wang Y F, Li X B, Liang R X et al. Simulation of a solid-phase oxygen control scheme in lead-bismuth eutectic system[J]. Nuclear Engineering and Design, 394, 111821(2022).

[77] Zhang Y, Zhang D L, Wang C L et al. Oxygen transport analysis in lead-bismuth eutectic coolant for solid-phase oxygen control[J]. Annals of Nuclear Energy, 154, 108128(2021).

[78] Gonzalez Prieto B, Lim J, Rosseel K et al. Polonium evaporation from liquid lead–bismuth eutectic with different oxygen content[J]. Journal of Radioanalytical and Nuclear Chemistry, 309, 597-605(2016).

[79] Gonzalez Prieto B, Van den Bosch J, Martens J A et al. Equilibrium evaporation of trace polonium from liquid lead–bismuth eutectic at high temperature[J]. Journal of Nuclear Materials, 450, 299-303(2014).

[80] Deng L L, Wang Y Q, Zhai Z A et al. Multi-physics model development for polonium transport behavior in a lead-cooled fast reactor[J]. Frontiers in Energy Research, 9, 711916(2021).

[81] Alhassan E, Sjöstrand H, Duan J et al. Combining total Monte Carlo and benchmarks for nuclear data uncertainty propagation on a lead fast reactor’s safety parameters[J]. Nuclear Data Sheets, 118, 542-544(2014).

[82] Romojaro P, Álvarez-Velarde F. Impact of nuclear data evaluations on data assimilation for an LFR[J]. EPJ Web of Conferences, 239, 13007(2020).

[83] Trottier A, Adams F P, Levinsky A et al. Nuclear data sensitivity for reactor physics parameters in a lead-cooled reactor[J]. Annals of Nuclear Energy, 120, 333-347(2018).

[84] Trivedi I, Hou J, Grasso G et al. Nuclear data uncertainty quantification and propagation for safety analysis of lead-cooled fast reactors[J]. Science and Technology of Nuclear Installations, 2020, 3961095(2020).

[85] TANG Mao, ZHAO Pengcheng, LI Wenjie et al. MBSE-based passive residual heat removal system for lead-cooled fast reactors design requirement analysis[J]. Nuclear Techniques, 47, 040602(2024).

[86] ZHOU Tao, TANG Jianyu, JIANG Yi. Sedimentation movement of particles in liquid lead-bismuth alloy reactor core channel based on grey correlation degree[J]. Nuclear Techniques, 46, 070603(2023).