The group primarily undertake the design of lead-bismuth reactor nuclear islands, research and development of key technologies, experimental verification, and the development of fuel assemblies. Our efforts provide solid technical support and talent assurance for the development of China's advanced nuclear energy systems and closed fuel cycle strategy.

1. Lead-bismuth reactor core & component design

2. Reactor thermal safety and engineering thermophysics

3. Lead-bismuth reactor system, equipment, and key technologies

4. Reactor materials and processes

5. Reactor testing and engineering verification

Academic/Conference paper:

[1] Zhao L, Zhang H, Liu X, et al. Corrosion of F/M steels and austenitic steels in Pb-Mg at different temperatures[J]. Nuclear Materials and Energy, 2024, 40: 101705.

[2] Zhang H, Liu X, Xu Y, et al. Comparison investigation on corrosion of SIMP and T91 steels exposed to liquid LBE at 450℃: The role of Si on reducing oxidation rate[J]. Corrosion Science, 2023, 225: 111553.

[3] Yao C, Zhang H, Chang H, et al. Structure of surface oxides on martensitic steel under simultaneous ion irradiation and molten LBE corrosion[J]. Corrosion Science, 2022, 195: 109953.

[4] Yao C, Wang Z, Zhang H, et al. HLMIF, a facility for investigating the synergistic effect of ion-irradiation and LBE corrosion[J]. Journal of Nuclear Materials, 2019, 523: 260-267.

[5] Zou Z, Huang S, Peng T, et al. Design and dynamic operation characteristics of phase-change thermal energy storage heating systems[J]. Applied Thermal Engineering, 2025: 128827.

[6] Tian W, Peng T, Fan X, et al. Numerical analysis of turbulent mixed convection heat transfer of molten salt in horizontal tubes with uniformly cooled heat flux[J]. International Journal of Heat and Mass Transfer, 2024, 228: 125630.

[7] Peng T, Wan J, Liu W, et al. Choice of hydrogen energy storage in salt caverns and horizontal cavern construction technology[J]. Journal of Energy Storage, 2023, 60: 106489.

[8] 彭天骥, 顾龙, 王大伟, 等. 中国加速器驱动嬗变研究装置次临界反应堆概念设计[J]. 原子能科学技术, 2017, 51(12): 2235-2241.

[9] 秦长平; 顾龙*; 李金阳; 加速器驱动的ADS次临界气冷快堆物理方案研究, 原子能科学技术, 2013, Vol.47 Supply, 592-595.

[10] Wangsheng Tian, Tianji Peng, et al. Numerical analysis of turbulent mixed convection heat transfer of molten salt in horizontal tubes with uniformly cooled heat flux[J]. International Journal of Heat and Mass Transfer, 2024, 228: 125630.

[11] Wangsheng Tian, Tianji Peng, et al. Numerical analysis of turbulent mixed convection heat transfer of molten salt in an inclined cooling tube[J]. Annals of Nuclear Energy, 2024, 207: 110676.

[12] Jin-Yang Li, Long Gu*, Zhi-Yong He, You-Peng Zhang, Hu-Shan Xu, Yang Sheng, Qin Changping, Wang Da-Wei, Fan Da-jun. The development and application of digital refueling mock-up for China initiative accelerator driven system. Progress in Nuclear Energy, 2020, 127, 103433.

[13] 李金阳; 顾龙*; 秦长平; 王大伟; 刘璐; 加速器驱动100MW快热耦合气冷堆物理方案研究, 原子能科学技术,2013, Vol.47 Supply, 208-211.

[14] 王大伟; 顾龙*; 李金阳; 秦长平; 加速器驱动的球床堆方案研究, 原子能科学技术, 2013, Vol.47 Supply, 596-598.

[15] Jinyang Li*; Long Gu*; Hu-Shan Xu; Nadezda Korepanova; Rui Yu; Yan-Lei Zhu; Changping Qin; CAD modeling study on FLUKA and OpenMC for accelerator driven system simulation, Annals of Nuclear Energy, 2013, Vol.114, 329-341.

[16] Rui Yu, Guan Wang, Wei Jiang, Yanlei Zhu, Changping Qin, Long Gu. Preliminary Verification of Key Physical Models in Oxide Fuel Performance Analysis Code FEATURE Based on COMSOL, Nuclear Science and Engineering, 199(4),569-577.

[17] Jinyang Li*; Long Gu*; Dawei Wang; Rui Yu; Xin Sheng; Yanlei Zhu; Lu Zhang; Changping Qin; Guan Wang. the three dimensional immersive training platform for china initiative accelerator driven subcritical system. Proceedings of the 2019 27th International Conference on Nuclear Engineering (ICONE27), Ibaraki, Japan, 2019-05-19至2019-05-24.

[18] Jinyang Li*; Long Gu*; Dawei Wang; Changping Qin; Neutronic Research on Gas-cooled Breeding Fast Reactor, 7th International Conference on Modelling and Simulation in Nuclear Science and Engineering (7ICMSNSE), Ottawa, Canada, 2015-10-18至2015-10-21.

Invention patent:

[1] 姚存峰,陈乐利,王志光,等.一种换热管及制备方法和在铅铋快堆中的应用:202510128970[P][2026-03-24].

[2] 姚存峰,王志光,张宏鹏,等.控氧液态铅铋腐蚀和离子辐照协作研究实验装置及方法:CN201810553367.4[P].CN108444900B[2026-03-24].

[3] 姚存峰,王志光,常海龙,等.离子辐照和液态金属腐蚀协同作用研究实验装置及方法:CN201310630224.6[P].CN103698262B[2026-03-24].

[4] 顾龙; 盛选禹; 李金阳; 王大伟; 范庆; 秦长平; 刘璐. 用于加速器驱动次临界核能系统的固体散列靶. 2013-11-13, 中国, ZL201320275946.X ZL201310186564.4

[5] 盛鑫; 顾龙; 于锐; 朱彦雷; 刘璐; 王大伟; 李金阳; 彭天骥; 张璐; 唐延泽; 秦长平; 范旭凯; 田旺盛; 姜韦; 李秀玲. 一种用于铅基反应堆燃料组件的换料抓头机构. 2020-7-7, 中国, ZL201910958002.1 (11/15)

[6] 盛鑫; 顾龙; 于锐; 朱彦雷; 刘璐; 王大伟; 李金阳; 彭天骥; 张璐; 唐延泽; 秦长平; 范旭凯; 田旺盛; 姜韦; 李秀玲. 一种铅基反应堆燃料组件的下管座浮力锁紧机构. 2020-7-7, 中国, ZL201910957810.9 (11/15)

[7] 盛鑫; 顾龙; 于锐; 朱彦雷; 刘璐; 王大伟; 李金阳; 彭天骥; 张璐; 唐延泽; 秦长平; 范旭凯; 田旺盛; 姜韦; 李秀玲. 一种铅基反应堆燃料组件的上管座自锁机构. 2020-7-7, 中国, ZL201910958021.7 (11/15)

[8] 盛鑫; 顾龙; 于锐; 朱彦雷; 刘璐; 王大伟; 李金阳; 彭天骥; 张璐; 唐延泽; 秦长平; 范旭凯; 田旺盛; 姜韦; 李秀玲. 一种铅基反应堆燃料组件的锁紧､解锁及抓取提升装置. 2020-7-14, 中国, ZL201910958005.8 (11/15)

[9] 朱彦雷; 顾龙; 于锐; 蔡以林; 彭天骥; 王大伟; 李金阳; 秦长平; 刘璐; 盛鑫; 唐延泽; 张璐; 田旺盛; 冯丽. 反应堆燃料组件的锁紧与提升机构以及锁紧与提升方法. 2019-7-19, 中国, CN108039214B ZL201711323628.5 (8/14)

[10] 范大军; 顾龙; 彭天骥; 唐延泽; 田旺盛; 盛鑫; 刘大孝; 文俊; 刘璐; 李金阳; 王大伟; 张璐; 于锐; 秦长平; 姜韦; 范旭凯; 崔青蓝. 一种具有内部螺旋槽纹的定位装置及其使用方法. 2020-11-10, 中国, ZL201811599315.7 (14/17)

[11] 范大军; 顾龙; 彭天骥; 唐延泽; 朱彦雷; 盛鑫; 刘璐; 李金阳; 王大伟; 张璐; 于锐; 秦长平; 田旺盛; 冯丽; 姜韦; 范旭凯. 一种具有外部螺旋槽纹的定位装置及其制作和使用方法. 2020-11-10, 中国, ZL201811472853.X (12/16)

[12] 田旺盛;彭天骥;范旭凯;唐延泽;秦长平;范德亮;盛鑫;朱彦雷;顾龙;张璐;孟海燕;李秀凌. 一种竖直管束结构液态铅铋-熔盐对流换热实验段及实验方法. 2025-03-25, 中国, ZL 202210490593.9 (5/9)

[13] 朱彦雷;盛鑫;范大军;顾龙;刘璐;唐延泽;秦长平;范旭凯彭天骥;王大伟;于锐;李金阳;张璐;田旺盛;姜韦;孟海燕. 一种燃料棒束的可视化热工流体实验装置. 2022-07-19, 中国, ZL 2020 1 0855449.1 (7/16)

[14] 刘璐;顾龙;朱彦雷,盛鑫;王大伟;李金阳;彭天骥;张璐于锐;唐延泽;秦长平;范旭凯;田旺盛;姜韦;孟海燕. 一种铅基反应堆燃料组件锁紧结构. 2022-09-16, 中国, ZL 2020 1 0565243.5 (11/15)

[15] 唐延泽;彭天骥;秦长平;顾龙;田旺盛:范旭凯;范德亮盛鑫,王大伟;孟海燕;李金阳;张璐,于锐;朱彦雷;刘璐. 一种用于液态铅基冷却剂过滤净化的冷阱装置. 2023-08-18, 中国, ZL 2021 1 0123594.5 (3/15)