Research divisions
1. Research fields（discipline development）
The division of reactor operation research is fully involved in the design, construction, commissioning, operation, and decommissioning stages of reactors. The division assists in the optimization of reactor design and is directly responsible for reactor operation safety. Reactor Commissioning Technology: Based on the characteristics of reactor technology, the division conducts research on commissioning technology and is responsible for commission process. The division completes commissioning for several reactors and obtains multiple commissioning technology achievements. Reactor operation technology: The division keeps deep ploughing on the operation technology of high-temperature gas cooled reactors and low-temperature heating reactors, comprehensively masters the operating characteristics of reactors, scientifically optimizes Operating Restrictions, and ensures reactor operation safety. Optimization design and aging mechanism research of key systems and equipment of reactors: By utilizing operational experience and continuous system equipment optimization, the safety and operability of reactors have been effectively improved. The division promote research on aging mechanism at the same time. Reactor decommissioning technology: Based on the Shielded swimming pool reactor decommissioning project, the division carries out the research on reactor decommissioning technology. Operator training: The division has established a preliminary operator training system, and completes multiple training tasks. |
2.Scientific research projects
The scientific research projects undertaken by the division of reactor operation research involve multiple topics in China National Science and Technology Major Project "Demonstration Project of Million Kilowatt Large Pressure Water Reactor and High Temperature Gas Cooled Reactor", key projects of the China National 863 Program, nuclear energy development research projects of the Science and Technology Bureau of China, China National Natural Science Foundation projects, and related horizontal projects in cooperation with domestic and foreign enterprises. (1) Experimental verification of multiple technical issues in demonstration projects using HTR-10 (China National Science and Technology Major Project) (2) Research on Nuclear Material Accounting Method for pebble Bed High Temperature Gas Cooled Reactor (Nuclear Energy Development Project) (3) Research and Safety Analysis of HTR-10 Ultra High Temperature Operation (China National Science and Technology Major Project) (4) Preliminary research on ultra-high temperature operation technology of HTR-10 (China National 863 Program) (5) Real time simulation of HTR-10 ultra-high temperature operating characteristics and verification experiments on the reactor (key research and development plan) (6) Research on the Mechanism and Transport Behavior of Radioactive Dust Based on HTR-10 (China Natural Science Foundation) (7) Performance and fission product data collection test for high temperature gas cooled reactor waste heat removal system (commissioned by enterprises and institutions) |
3.Reactors and Laboratories
The division of reactor operation research dedicates to the reactor operation management, experimental research, technological development and research on the comprehensive utilization of multiple research reactors, including swimming pool shielded test reactor, HTR-5, and HTR-10. The swimming pool shielded test reactor was built in 1964, with a building area of 7656 m2. We have completed multiple testing tasks, including shielding material testing, mono crystalline silicon irradiation doping testing, radiation resistant material reinforcement testing, neutron photography testing, nuclear heating testing, etc. It was awarded the China National Science Conference in 1978. This reactor is currently in the decommissioning stage. The NHR-5 was built in 1989, with a building area of 1026 m2. It is the first reactor in the world to adopt a tight fitting double-layer pressure shell, full power natural circulation, and hydraulic driven control rods. It has successfully completed experimental tasks such as heating, power generation, co-generation, and refrigeration. It was awarded the Special Prize for Science and Technology Progress by the China National Education Commission in 1991, the First Prize for National Science and Technology Progress in 1992, and the Second Prize for National Technology Invention. It was selected as one of the Top Ten China National Science and Technology News in 1989 and the Top Ten World Science and Technology Achievements in 1990. The HTR-10 is one of the key projects of the China National "863" high-tech Program, with a building area of 5925 m2. It reached first criticality in 2000 and achieved full power operation by the end of 2002. Among the design and research achievements, over 30 have passed technical evaluations, including physical design research, graphite performance research, helium technology and helium loop, fuel element development, full-scale simulation experimental equipment for fuel handling and unloading and pebble bed characteristics research, performance of hot gas duct and steam generator, and all digital reactor protection system. Among them, 16 have reached the international advanced level or international level, and 14 achievements have won China national or ministerial level awards. |
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swimming pool shielded test reactor |
HTR-10 |
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NHR-5 |
Main control room of HTR-10 |
4.Academic achievements (articles, rewards)
Awards: The 10 MW high-temperature gas cooled reactor test module: the first prize of the China National Science and Technology Progress Award in 2006 The 10 MW high-temperature gas cooled reactor test module: the first prize for scientific and technological progress from the China Ministry of Education in 2004 The 5 MW low-temperature nuclear heating reactor: the second prize of the China National Technology Invention Award in 1992 The 5 MW low-temperature nuclear heating reactor: the first prize of the China National Science and Technology Progress Award in 1992 The 5 MW low-temperature nuclear heating reactor: the 1991 China National Education Commission Science and Technology Progress Special Prize Swimming pool shielded test reactor: the China National Science Conference Award in 1978 |
Articles： The division has published about 10 articles annually in recent years. [1] HE X, YIN H, DU B, et al. High Temperature Corrosion Behavior of Inconel 617 in Environment of Impure Heli[J]. Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2024,58(1): 189-197. [2] DU B, ZHANG H, ZHENG W, et al. Carburization and tensile behavior of Alloy 617 in impure helium containing a part-per-million level of CH4 at 950 °C[J]. Corrosion Science, 2024,227. [3] LIU R, LI H, ZHANG H, et al. Study on tritium permeation behavior in primary and second circuits of the hydrogen production system by methane steam reforming using HTGR[J]. Nuclear Engineering and Design, 2024,421. [4] ZHANG H, ZHANG W, ZHANG L, et al. Estimation of transuranic isotopes in irradiated fuel elements for pebble bed HTR on activity vector[J]. Progress in Nuclear Energy, 2024,168. [5] LI H, ZHENG W, DU B, et al. Study on Corrosion Behavior of T-22 Alloy in Ultrahigh Temperature Impure Helium and Air[C]//. Springer Proceedings in Physics, 2023: 1140-1148. [6] ZHANG Y, FANG X, JIANG S, et al. The direct measurement of HTR-10 in-core neutron flux[J]. Nuclear Engineering and Design, 2023,401. [7] ZHENG W, LI H, DU B, et al. High-temperature reaction kinetics of Inconel 617 in impure helium[J]. Nuclear Materials and Energy, 2023,34. [8] ZHENG W, DU B, LI H, et al. High temperature corrosion of two superalloys in the impure helium environment[J]. Journal of Nuclear Science and Technology, 2023,60(8): 923-929. [9] LI H, DU B, ZHENG W, et al. Study on corrosion behavior of two superalloys under two extreme atmospheres[J]. Annals of Nuclear Energy, 2023,181. [10] WANG J, HAO Y, LI Y, et al. COMMISSIONING TEST STUDY ON RESIDUAL HEAT REMOVAL VENTILATION IN SPENT FUEL CANISTER UNLOADING STAGE OF HTR-PM PROJECT[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2023. [11] ZHENG W, LI H, DU B, et al. INFLUENCE OF CO AND CO2 LEVELS IN IMPURE HELIUM ON THE HIGH TEMPERATURE CORROSION BEHAVIOR OF INCONEL 617[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2023. [12] PENG L, ZHANG S, ZHANG H, et al. Study on tortuosity from 3D images of nuclear graphite grades IG-110 by Dijkstra's algorithm and fast marching algorithm[J]. Powder Technology, 2023,427. [13] DU B, LI H, ZHENG W, et al. Study of oxidation behavior and tensile properties of candidate superalloys in the air ingress simulation scenario[J]. Nuclear Engineering and Technology, 2023,55(1): 71-79. [14] HAO Y, LI Y, WANG J, et al. Structure-Performance-Cost Integration Multi-Objective Optimization Design for HTR Fuel Storage Canister[J]. Hedongli Gongcheng/Nuclear Power Engineering, 2023,44(2): 145-151. [15] HAO Y, WANG J, LIN M, et al. Hybrid Surrogate Model-Based Multi-Objective Lightweight Optimization of Spherical Fuel Element Canister[J]. Energies, 2023,16(8). [16] LI H, DU B, ZHENG W, et al. CORROSION STUDY OF INCONEL 617 ALLOY IN HTGR WITH IMPURE HELIUM ATMOSPHERE[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2023. [17] DU B, CHENG H, LI H, et al. EFFECT OF METHANE IN HELIUM ON THE TENSILE PROPERTY OF SUPERALLOYS FOR VERY HIGH-TEMPERATURE REACTOR APPLICATIONS[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2023. [17] ZHANG H, ZHANG L, XIAO H, et al. ESTIMATION OF IRRADIATION HISTORY OF FUEL SPHERES IN HTR-PM BASED ON GENETIC ALGORITHM[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2023. [17] GONG M, WANG J, HAO Y, et al. CFD SIMULATION OF A SCALED MODEL OF THE STORAGE WELL IN SPENT FUEL DRY-STORAGE SYSTEM OF HTR-PM600[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2023. [18] LI H, ZHENG W, DU B, et al. The high temperature corrosion of Incoloy 800H alloy at three different atmospheres[J]. Journal of Nuclear Science and Technology, 2023,60(2): 165-174. [19] ZHENG W, ZHANG H, DU B, et al. Effect of impurity ratios on the high-temperature corrosion of Inconel 617 and Incoloy 800H in impure helium[J]. Annals of Nuclear Energy, 2023,189. [20] LI H, ZHENG W, DU B, et al. Study on corrosion of T-22 alloy under high temperature condition of VHTR[J]. Journal of Nuclear Science and Technology, 2023,60(9): 1070-1078. [21] LI H, ZHANG H, ZHENG W, et al. Study on oxidation kinetics of three kinds of candidate superalloys for VHTR under air ingress accident[J]. Annals of Nuclear Energy, 2023,189. [22] HAO Y, WANG J, WU B, et al. Study on the most severe condition for structural assessment of nuclear fuel transport package under impact loading[J]. Progress in Nuclear Energy, 2022,153. [23] DU B, YIN H, LI H, et al. Preliminary study on corrosion behavior and mechanical properties of inconel 617 in impure helium environment of vhtr[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2022. [24] LI H, ZHENG W, YIN H, et al. Study on Decarburization and Oxidation Corrosion Behavior of T-22 Alloy in Impure Helium of High-temperature Gas-cooled Reactor[J]. Hedongli Gongcheng/Nuclear Power Engineering, 2022,43(4): 38-45. [25] LI H, ZHENG W, DU B, et al. Effect of a cr2o3/-Al2o3 coating on the corrosion behavior of incoloy 800h alloy in high temperature impure helium[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2022. [26] HAO Y, LI Y, WU B, et al. Optimization analysis of HTR-PM600 fresh fuel transport container under multiple impact loading conditions[J]. Annals of Nuclear Energy, 2022,175. [27] WU B, WANG J, LI Y, et al. Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM[J]. Science and Technology of Nuclear Installations, 2022,2022. [28] HAO Y, LI Y, LIN M, et al. Containment Integrity and Sealing Assessment for HTR-PM600 Fresh Fuel Transport Package Under Impact Loading[J]. Frontiers in Energy Research, 2022,10. [29] ZHENG W, ZHANG H, DU B, et al. High-Temperature Corrosion Behavior of Incoloy 800H Alloy in the Impure Helium Environment[J]. Science and Technology of Nuclear Installations, 2022,2022. [30] LI H, ZHENG W, YIN H, et al. Effect of Pre-oxidation on Corrosion Behavior of Three Kinds of Superalloys in Impure Helium of High-temperature Reactor[J]. Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2022,56(6): 1069-1077. [31] LI J, WEI L, ZHENG Y, et al. Experimental study on the residual heat removal system in HTR-10[C]//. Journal of Physics: Conference Series, 2021. [32] WANG F, WEI L, KANG T, et al. Experimental study on performance improvement of HTR-10 helium purification system[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2021. [33] WANG F, CHEN X, XIE F, et al. Experimental design on performance improvement of the helium purification system of HTR-10[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2019. [34] WEI L, DING D, LIU L, et al. Characteristic tests on transition core of HTR-10[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2018. [35] WEI L, XIE F, CHEN X, et al. Summary and experience feedback on the restart and power operation After a long term shutdown of HTR-10[C]//. International Topical Meeting on High Temperature Reactor Technology, HTR 2016, 2016: 218-223. |
5.Members
| Name | Direction | ||
| Research Members | HUANG Peng | chphuang@tsinghua.edu.cn | Commissioning, operation |
| MA Tao | mt@tsinghua.edu.cn | Decommissioning, operation | |
| CHEN Xiaoming | chenxm@tsinghua.edu.cn | Operation technology | |
| WEI Liqiang | weilq@tsinghua.edu.cn | Dommissioning, operation | |
| JIA Lixin | klizn@tsinghua.edu.cn | Aging management | |
| WANG Yucheng | wangyucheng@tsinghua.edu,.cn | Dommissioning, operation | |
| ZHU Jiang | zhujiang@tsinghua.edu.cn | Process planning | |
| LIU ling | liuling@tsinghua.edu.cn | Maintenance technology | |
| LI Zhihui | zhihui-li@tsinghua.edu.cn | Process planning | |
| YANG Hongwei | yang-hw@tsinghua.edu.cn | Operation, maintenance | |
| ZHONG Wei | zty928-26@163.com.cn | Operation, maintenance |
