Research
1、Research fields (discipline construction)
The division is in charge of the general design, design coordination and design management of High Temperature gas-cooled reactor (HTGR) projects in the Institute of Nuclear and New Energy Technology (INET), Tsinghua University. The division has been responsible for the general design of the 10MWth high temperature Gas-cooled Reactor—Test Module (HTR-10), the general design of the 200MWe High Temperature Gas-cooled Reactor—Pebble-bed Module (HTR-PM) project, and is currently undertaking the general design of important equipment and systems for the nuclear island of the HTGR commercial engineering projects. As the nucleus and functional department for HTGR design, the division starts from the general perspective of the project and carries out relevant work including general plan research and implementation, design management, design coordination and interface parameter management on the basis of summarizing the relevant designs of each major of the project. Finally the division formulates the general design proposal of HTR-PM. HTGR has significant advantages, including inherent safety characteristics, high power generation efficiency, hydrogen production capabilities. It can also be used for a variety of process heat applications. It is considered to be one of the preferred reactor types for the Generation IV nuclear energy system. It has reserved broad recognition and emphasized development internationally and domestically. Chinese government has long-term support for the development of HTGRs as one of national science and technology major programs. The division is directly responsible for the general design of the HTGRs of INET. The division's research spans all disciplines related to HTGR nuclear power plants, merging theory with practice and balancing professional technology with the overarching structure of HTGR system. At the same time, the division also maintains frequent and efficient academic exchanges and scientific research cooperation with domestic and foreign research institutions. |
2、Research projects
Design and research of the 200MWe High Temperature Gas-cooled Reactor—Pebble-bed Module (HTR-PM) project Key elements of research Based on reactor physics, thermohydraulics, safety analysis, structure, control, etc.: ● HTGR general scheme and system research ● HTGR safety concept ● Development of innovative reactor types ● Process heat applications based on HTGR ● Project management of HTGR design |
3、Academic achievements (papers, awards)
Main awards: 2018 China Nuclear Energy Industry Association Science and Technology Award, Second Prize, Development of new fuel element transportation and storage containers for HTGRs 2016 China Nuclear Energy Industry Association Science and Technology Award, First Prize, Research on Key Technologies for Nuclear Power Plant Earthquake Safety 2007 National Science and Technology Progress Award, First Prize, 10MW High Temperature Gas-cooled Test Reactor 2004 Ministry of Education Science and Technology Progress Award, First Prize, 10MW High Temperature Gas-cooled Test Reactor |
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Academic papers: Li F, Chen FB, Wang HT, et al. One implementation of vented low pressure containment for HTR. Nuclear Engineering and Design, 2020, 356: 110412. Zhang ZY, Dong YJ, Qi WW, Sun J. HTR-PM: Making dreams come true. Nuclear Engineering International [J], 2019, 64(775): 16-18. Zhang ZY, Dong YJ, Li F, et al. The Shandong Shidao Bay 200 MWe High-Temperature Gas-Cooled Reactor Pebble-Bed Module (HTR-PM) Demonstration Power Plant: An Engineering and Technological Innovation [J]. Engineering, 2016, 2(1): 112-118. Zhang ZY, Wu ZX, Wang DZ, Xu YH, Sun YL, Li F, Dong YJ. Current status and technical description of Chinese 2 x 250 MWth HTR-PM demonstration plant [J]. Nuclear Engineering and Design, 2009, 239(7): 1212-1219. The division publishes about 20 academic papers every year. |
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Research accomplishments: 1) 10MWth High Temperature Gas-cooled Reactor—Test Module (HTR-10) With the support of the national ‘863’ program, our institute has carried out research and development of the 10MW High Temperature Gas-cooled Reactor—Test Module (HTR-10) since the mid-1980s. HTR-10 reached criticality in December 2000 and achieved full load grid-connected power generation in January 2003.
2) 200MWe High Temperature Gas-cooled Reactor—Pebble-bed Module (HTR-PM) HTR-PM is a demonstration project of the High Temperature Gas-cooled Reactor sub-project of the National Science and Technology Major Project ‘Large Advanced Pressurized Water Reactor and High Temperature Gas-cooled Reactor Nuclear Power Plant’. Based on the HTR-10 that has been built and operated in China, the goal of the High Temperature Gas-cooled Reactor sub-item determined in the general implementation plan approved by the State Council is to construct a 200MW High Temperature Gas-cooled Reactor —— Pebble-bed Module (HTR-PM) with independent intellectual property rights by overcoming the industrial amplification and engineering experimental verification technology of HTGRs and the batch preparation technology of high-performance fuel elements. Research on technologies such as helium turbine direct cycle power generation and HTGR hydrogen production are carried out, laying the foundation for the development of fourth-generation nuclear power technology. The demonstration project includes two pebble-bed modular HTGRs and a turbine-generator unit. On December 9, 2012, the National Nuclear Safety Administration issued a demonstration project construction permit and the first concrete for the nuclear island was poured. On August 20, 2021, the operation license was obtained and fuel loading started. On December 20, 2021, it was connected to the grid to generate electricity. In December 2022, it reached the initial full power. On December 6, 2023, it was officially put into commercial operation.
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5、Team members
Name |
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Dong Yujie |
dongyj@tsinghua.edu.cn |
Wang Haitao |
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Sun Yuliang |
sunyl@tsinghua.edu.cn |
Chen Zhipeng |
zhipeng@tsingha.edu.cn |
Chen Fubing |
chenfubing@tsinghua.edu.cn |
Huang Zhiyong |
huangzy@tsinghua.edu.cn |
Wang Xin |
wangxinw@tsinghua.edu.cn |
Quan Ying |
quanying@tsinghua.edu.cn |
Qin Xuying |
qinxuying@tsinghua.edu.cn |
Sun Jisong |
sunjs@sem.tsinghua.edu.cn |
