Research divisions
1. Research Fields (Discipline Construction)
The Division of Reactor Structure is based on the high temperature gas-cooled reactors, cryogenic heating reactors and high flux reactors designed and developed by The Institute of Nuclear and New Energy Technology (INET), and its scientific research fields concentrate on the research and development of key equipment of the reactor body as well as nuclear safety-grade systems and circuits. The main research fields include: (1)Reactor pressure vessels; (2)High-temperature gas-cooled reactor metal, graphite and carbon brick in-heap components; (3) Heat exchangers and steam generators; (4) Nuclear piping systems, including reactor first and second circuits, nuclear safety pumps and valves; (5)New control rod drive system. The discipline construction is nuclear science and technology (primary discipline) nuclear energy science and engineering (secondary discipline) Research directions include: (1)Structural optimisation of the design of reactor systems and components; (2)Integrity assessment of pressure vessels; (3)Pre-breakage leakage analysis techniques for pressure vessels and pipelines; (4)Performance study and life assessment of graphite structural materials for reactors; (5)Seismic performance study of bulk structure; (6)Research and development of new heat exchanger and steam generator systems; (7)Soil-structure interaction and floor reaction spectrum generation techniques; (8)Mechanical analysis techniques for large-scale structures; (9)Research on rapid numerical analysis techniques for large-scale flow and heat transfer; (10)Seismic analysis techniques for components and systems; (11)Research on fluid-induced vibration; (12)Particle dynamics of graphite in high-temperature gas-cooled reactors; (13)Research on analysis techniques for key equipment of new-generation pressurised water reactor nuclear power plants; (14)Computer-aided design (CAD) of engineering structures; (15)Research and Development of New Control Rod Drive System, etc. |
2. Research Projects
The Division of Reactor Structure carries out research activities mainly focusing on the high-temperature gas-cooled reactors and low-temperature heating reactors developed by INET, and lays a solid foundation for the research and development of these two new types of reactors. In the new century, INET has carried out the design and construction of many reactor projects, including the NP project, the helium turbine cycle experimental setup for high temperature gas-cooled reactors (HTR-10-GT) project, the high-temperature gas-cooled reactor demonstration power plant (HTR-PM) project, the integral advanced pressurized water reactor project, etc. In addition to the design and analysis of key equipment and systems, the laboratory also undertakes research projects on two subjects in the major special project for high-temperature gas-cooled reactor nuclear power plants. National 12th five-year major scientific and technological projects: (1)Spiral tube once-through steam generator key technology research and engineering verification (2)Major Project “Dynamic Response and Structural Integrity of Graphite Intra-heap Components”. National 13th five-year major scientific and technological projects: (1)Study on the Key Process and Application Performance of UNS N06625 for High Temperature Gas-cooled Reactor Steam Generator Localization (2)Optimisation of Design and Manufacturing Technologies for High Temperature Gas-cooled Reactor Key Equipment (3)Research and development of intermediate heat exchanger for high-temperature reactors and verification of key technologies (4)Development of nuclear-grade helium isolation valve for high-temperature gas-cooled reactor (5)Sub-theme of “Study on design optimisation and standardisation of multi-module high-temperature gas-cooled reactors”: Seismic design of nuclear island key equipment and sub-theme of “Study on implementability of in-service inspection of multi-module high-temperature gas-cooled reactors” (6)Sub-topic of “Expanded Performance Tests of Important Equipment for High-Temperature Reactor Demonstration Project”: Expanded Performance Tests of Evaporator (7) Study of rheological vibration test technology for steam generator connecting tube bundles, a sub-topic of “Study of key technologies for commissioning high-temperature reactor demonstration projects” (8)Study on “Multi-module High-temperature Reactor Pile Foundation and Large Aircraft Impact Resistance Analysis”, sub-topic: Analysis of the impact of aircraft impact on key equipment of multi-module high-temperature reactors, and sub-topic: Seismic vulnerability analysis of key equipment of multi-module high-temperature reactors. |
3.Laboratory and Equipment
The research task of the Division of Reactor Structure is mainly on the research and development of nuclear safety equipment and systems. According to the requirements of nuclear safety regulations, a large number of calculations and analyses need to be carried out for all kinds of equipment and systems in the research and development work. In order to meet the demands of scientific research, the Division has gradually equipped itself with a complete set of structural and thermal calculation software, which are mainly commercial software of international renown. These analysis software basically meets the technical requirements of mechanical analysis of equipment structure, piping system analysis, thermal analysis, multi-system coupling analysis and other aspects. While constructing the software system, the Division has also provided good computer conditions to ensure an outstanding application platform for the software system. At present, each researcher of the Division owns a high-performance microcomputer, at the same time, the Division is also specially configured with two IBM servers and an integrated blade server, which are specially used for large-scale analyses and calculations, and in order to cooperate with these servers to carry out large-scale calculations, there are also three sets of high-performance HP workstations for before and after processing of the calculations. The above hardware and software conditions have guaranteed that the Division has sufficient capacity to carry out large-scale structural statics and dynamics analyses, highly nonlinear structural mechanics analyses, thermal analyses, multi-physics field coupling analyses, fracture mechanics and structural reliability analyses, and analyses of fluid transport systems. At present, the Division has realized the organic combination of research, design and calculation, which improves the working efficiency and design level, reduces the interference of human factors, and provides excellent technical guarantee for the achievement of R&D objectives. |
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HTR-PM One Circuit Pressure Boundary Finite element analysis (triple shell and its support) |
HTR-PM Evaporator Full-Size Heat Transfer Unit Test Circuit |
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Graphite and carbon in-stack component modelling load tests |
Finite element analysis evaluation of graphite and carbon in-stack components |
4. Academic Achievements (Articles, Awards)
Main Awards The 5MW Nuclear Heating Reactor (NHR-5) and the 10 MW High Temperature Gas-cooled Test Reactor (HTR-10) built in the last century are the achievements of many years of scientific research and development of the Division, and these two projects have won numerous national awards, which were awarded to several members of the Division. (1)In 2022, the First Prize of Scientific and Technological Progress of the China Nuclear Energy Association: Research on the Manufacturing Technology and Engineering Application of High Temperature Gas-cooled Reactor Steam Generator (2)In 2021, Scientific and Technological Achievement Award of Chinese Nuclear Society: Thermo-Hydraulic and Engineering Verification Tests of High Temperature Gas-Cooled Reactor Spiral Tube DC Steam Generator (3)In 2020, Second Prize of Shanghai Science and Technology Progress: The World's First -200WM High Temperature Gas-Cooled Nuclear Reactor Pressure Vessel Independence (4)In 2019, First Prize of Jiangsu Provincial Scientific and Technological Progress: Development and Industrialization of Key Tubes and Core Components for Advanced Nuclear Energy System (5)Outstanding Thesis Award for Key Laboratories of the Ministry of Education, 7 people (6)School-level advanced individual 2 people (7)Faculty-level advanced group 2 times (8)Faculty-level advanced individual 10 times |
Academic Papers Total number of publications: 171 (1)79 articles in international core journals (2)30 articles in domestic core journals, including 71 articles in SCI and 33 articles in EI. (3)28 articles in international conferences, and 24 teachers participated in international academic exchanges. (4)34 articles in domestic conferences, 25 teachers participated in domestic academic exchanges. Among them, 4 articles are listed in ISTP and 13 articles are listed in EI. |
Main Research Achievements (1)High Temperature Reactor Series Project: The demonstration High Temperature Gas-Cooled Reactor-Pebble-bed Module (HTR-PM) project has gradually entered the stage of installation, commissioning, criticality and power generation, as well as commercial operation. Room 104, as the unit responsible for the design of the main equipment, the first and second circuits, as well as the main process system and the special safety system, has the people in charge of the design projects shuttling to and from the manufacturing plants and the project sites to provide technical services, and has travelled between 200 and 300 people per year to solve various problems in manufacturing and installation and commissioning; theoretically predicts various transient conditions and possible accidents, and gives solutions. Due to the manufacturing problems of equipment manufacturers, the nuclear safety review department raised a series of questions before issuing the operating licence for HTR-PM, and some of the questions had to be demonstrated through the expert meeting with the Safety Bureau. The professionals in Room 104 fully cooperated with the company owner, and demonstrated, analyzed, and gave the technical routes to solve each question, and comprehensively answered all kinds of questions raised by the safety review department. They have made significant contributions to the commissioning, criticality and power up generation of HTR-PM. 600,000 high temperature gas-cooled reactor series project has made significant progress with the demonstration project, which has opened up a wide field for the commercial application of high temperature gas-cooled reactors, and in the past five years, 600,000 high temperature gas-cooled reactors series project has been carried out the preliminary and construction design, and summarized the design items in charge of the completed preparation documents and construction drawings as shown in Table 7. Each design catalogue are dozens or hundreds of parts and components of the diagrams. Applied for 23 domestic patents, approved 10 invention patents, entered into substantive examination of 13 invention patents. International invention patents were granted in Brazil, India, Malaysia, and Europe after 2019; previously in South Africa, Japan, Korea, Russia, Canada, and the United States, for a total of 10. (2)Low Temperature Reactor Project: As the main equipment and intermediate circuit of the 112 low-temperature reactor project, Room 104, the main unit, the person in charge of each design item in the past five years to stick to the installation and commissioning site, for the 112 project installation, commissioning, criticality and to achieve the power to provide comprehensive technical support. They have made great contributions to the successful completion and acceptance of Project 112. Low-temperature reactor XH and 200MW project, take 112 acceptance as a milestone, low-temperature reactor ushered in the development opportunity, XH and 200MW project was approved, nearly 5 years to carry out the preliminary design and construction design, summary of the design project is responsible for the completion of the preparation of documents and construction drawings, as shown in Table 8. Each design catalogue are dozens or hundreds of parts and components of the diagrams. (3)High-Flux Reactor: Structural design: completed reactor body 3D model, pressure vessel 3D model and reactor components 3D model design; completed pressure vessel component drawings and reactor components component drawings at the feasibility study stage (for feasibility study enquiry). The design documents: completed for the pressure vessel, reactor components, fuel handling and storage system feasibility study report (general provisions and process sub-sections); the design specifications for the pressure vessel, reactor components, fuel handling and storage system are completed and passed the evaluation. Calculation and analysis: completed the preliminary seismic analysis of the pressure vessel and reactor components, including the seismic analysis of the pressure vessel in the pool; completed the preliminary calculation of the flow distribution in the reactor; completed the preliminary numerical simulation of the critical flow rate in the core area. Scientific research and test: completed the development of remote operation robot arm for irradiated tanks in the reactor, “Intelligent realization of high-precision irradiated vessel loading and unloading equipment and development of principle prototype”, and passed the acceptance test. |
5 Group members
| No. | Position | Name | Contact Information (E-mail) |
| (1) | Director | 孙立斌 Sun Libin | slb@tsinghua.edu.cn |
| (2) | Branch Secretary | 李晓伟 Li Xiaowei | lixiaowei@tsinghua.edu.cn |
| (3) | Deputy Director / Commissary in Charge of Publicity | 闵琪 Min Qi | minq86@tsinghua.edu.cn |
| (4) | Deputy Director | 李笑天 Li Xiaotian | lixiaotian@tsinghua.edu.cn |
| (5) | Deputy Director | 史力 Shi Li | shili@tsinghua.edu.cn |
| (6) | Commissary in Charge of Organization | 柳雄斌Liu Xiongbin | lxb@tsinghua.edu.cn |
| (7) | Commissary in Charge of Discipline | 周钦 Zhou Qin | qinzhou@tsinghua.edu.cn |
| (8) | Commissary in Charge of Youth Committee | 李庠儒 Li Xiangru | lixiangru@tsinghua.edu.cn |
| (9) | 吴莘馨 Wu Xinxin | xinxin@tsinghua.edu.cn | |
| (10) | 张征明 Zhang Zhengming | zhzminet@tsinghua.edu.cn | |
| (11) | 雒晓卫 Luo Xiaowei | xwluo@tsinghua.edu.cn | |
| (12) | 阎慧杰 Yan Huijie | yanhj@tsinghua.edu.cn | |
| (13) | 顾永鹏 Gu Yongpeng | guyp@tsinghua.edu.cn | |
| (14) | 庄素芬 Zhuang Sufen | zhuangsufen@tsinghua.edu.cn | |
| (15) | 刘吉 Liu Ji | jiliu@tsinghua.edu.cn | |
| (16) | 朱超逸 Zhu Chaoyi | zhuchaoyi@mail.tsinghua.edu.cn | |
| (17) | 傅激扬Fu Jiyang | fujiyang@tsinghua.edu.cn | |
| (18) | 万力 Wan Li | liwan@tsinghua.edu.cn | |
| (19) | 张丽 Zhang Li | li-zhang@tsinghua.edu.cn | |
| (20) | 宋宇 Song Yu | songy@tsinghua.edu.cn | |
| (21) | 王晓欣 Wang Xiaoxin | wang-xiaoxin@tsinghua.edu.cn | |
| (22) | 栗志杰Li Zhijie | lizhijie1966@mail.tsinghua.edu.cn | |
| (23) | 王洪涛 Wang Hongtao | wanghongtao@tsinghua.edu.cn | |
| (24) | 胡梦佳 Hu Mengjia | humengjia@mail.tsinghua.edu.cn | |
| (25) | 赵加清 Zhao Jiaqing | jqzhao@tsinghua.edu.cn | |
| (26) | 张易阳 Zhang yiyang | zhangyiyang@tsinghua.edu.cn | |
| (27) | 张乾 Zhang qian | zhangq107@mail.tsinghua.edu.cn | |
| (28) | 翟婷 Zhai Ting | 2857245996@qq.com | |
| (29) | 马媛媛 Ma yuanyuan | mayuanyuan@tsinghua.edu.cn | |
| (30) | 周杰 Zhou Jie | zhoujie2022@tsinghua.edu.cn | |
| (31) | 彭恒 Peng Heng | peng_h@tsinghua.edu.cn | |
| (32) | 秦亥琦 Qin Haiqi | qinhq@mail.tsinghua.edu.cn | |
| (33) | 朱宏晔 Zhu Hongye | zhuhy@tsinghua.edu.cn | |
| (34) | 鲍宏琛 Bao Hongchen | baohongchen@tsinghua.edu.cn | |
| (35) | 席泽 Xi Ze | xize@mail.tsinghua.edu.cn | |
| (36) | 张海翔 Zhang Haixiang | zhanghx@tsinghua.edu.cn | |
| (37) | 周俊杰 Zhou Junjie | zhoujunjie@tsinghua.edu.cn | |
| (38) | 苏阳 Su Yang | yangsu@tsinghua.edu.cn | |
| (39) | 王贤刚 Wang Xiangang | wangxiangang@tsinghua.edu.cn | |
| (40) | 马笑辉 Ma Xiaohui | maxiaohui_1990@163.com | |
| (41) | 董言雨 Dong Yanyu | daxian168@126.com | |
| (42) | 尹燕楠 Yin Yannan | 570502873@qq.com |
