China, People’s Republic of
Progress of the HTR-10 project
Zhong, D.; Xu, Y. (Qinghua Univ., Beijing, BJ (China). Inst. of Nuclear Energy
Technology)
IAEA-TECDOC--899, pp:25-29
Design of indirect gas turbine cycle for a modular high temperature gas cooled reactor
Zhang, Z.; Jiang, Z. (Qinghua Univ., Beijing, BJ (China). Inst. of Nuclear Energy
Technology)
IAEA-TECDOC--899, pp:85-93
HTR-10 severe accident management
Xu Yuanhui; Sun Yuliang (Institute of Nuclear Energy Technology, Beijing (China))
IAEA-TECDOC--988, pp:93-100
Investigation of GT-ST combined cycle in HTR-10 reactor
Gao, Z.; Zhang, Z.; Wang, D. (Qinghua Univ., Beijing, BJ (China). Inst. of Nuclear Energy
Technology)
IAEA-TECDOC--899, pp:111-119
On the issues of fuel storage and decommissioning of the
HTR-10 test reactor
Sun Yuliang; Xu Yuanhui (Institute of Nuclear
Energy Technology, Tsinghua Univ., Beijing (China))
IAEA-TECDOC--1043, pp:133-139
Licensing experience of the HTR-10 test reactor
Sun, Y.; Xu, Y. (Qinghua Univ., Beijing, BJ (China). Inst. of Nuclear Energy Technology)
IAEA-TECDOC--899, pp:157-162
HTR-10 engineering experiments
Xu Yuanhui; Yao Meisheng; Liu Jiguo; Zhuo Huizhong; Ju Huaimin (Institute of Nuclear Energy Technology, Beijing (China))
IAEA-TECDOC--988, pp:321-332
Development of the graphite matrix materials of the fuel elements for the 10 MW HTR test module
Qiu Xueliang; He Jun; Guo Guiju; Zuo Kaifer;
Zhang Shuangxi (Tsinghua Univ., Beijing (China).
Inst. of Nuclear Energy Technology)
IAEA-TECDOC--901, pp:341-349
Oxidation behaviour of the matrix materials
Qiu Xueliang; He Jun; Ma Changwen (Tsinghua
Univ., Beijing (China). Inst. of Nuclear Energy
Technology); Zhang Shichao (Beijing Univ. of
Aeronautics and Astronautics, Beijing (China).
Dept. of Materials Science and Engineering)
IAEA-TECDOC--901, pp:351-362
Chinese Point and Status
Y. Xu, INET, Tsinghua University, China
HTR-2002, pp:1-8
Thermodynamic assessment of plant efficiencies for HTR power conversion
W. Fröhling, H. M. Unger, Research Centre Jülich, Germany and Y. Dong, Institute of Nuclear Energy Technology, Tsinghua University, China
HTR-2002, pp:1-5
Nuclear Emergency Planning and Preparedness for the HTR-10
J. Qu and Z. Wu, Institute of Nuclear Energy Technology, Tsinghua University, China
HTR-2002, pp:1-5
The measurement of burn-up level in HTR-10
L. Zhengpei, I. Wenfeng, H. Song and L. Fu, Institute of Nuclear Energy Technology, Tsinghua University, China
HTR-2002, pp:1-5
An In-Depth Study on Oscillation Peculiarities by Step-Input of Reactivity and Frequency of Helium Fan’s Transducer of 10 MW High Temperature Gas-Cooled Reactor and its Control Strategy
X. Huang, Institute of Nuclear Energy Technology, Tsinghua University, China
HTR-2002, pp:1-5
Stress and Seismic Calculation of HTR-10 SG Accident Discharge System
J. Gong, J. Fu and S. Yu, Institute of Nuclear Energy Technology, Tsinghua University, China
HTR-2002, pp:1-5
Introduction of HTR-10 Development (STAGE II)
Yingsu Wang, Huaneng Energy and Communications Co. Ltd.
HTR-2004, pp:1-3
Physical Designs and Calculations For The First Full Power Operation of The 10MW High Temperature Gascooled Reactor-Test Module (HTR-10)
Jing Xingqing, Yang Yongwei, Institute of Nuclear Energy Technology, Beijing, CHINA
HTR-2004, pp:1-7
Flow Field Analysis of the Hot gas chamber of the 10 MW High Temperature Reactor
Jinhua Wang, Zhiyong Huang, Hanliang Bo, Shengyao Jiang, Institute of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-10
Analysis of HTR-10 First Criticality with Monte Carlo Code Tripoli-4.3
Hong Chang, Xingqing Jing, Yongwei Yang, Institute of Nuclear Energy and Technology, Beijing, CHINA; Xaxier Raepsaet, Frederic Damian, Yi-Kang Lee, CEA-Saclay, Gif-sur-Yvette Cedex, FRANCE; Oliver Köberl, CEA-Cadarache, Saint Paul lez Durance, FRANCE
HTR-2004, pp:1-10
Comparison of Fuel Loading Pattern In HTR-PM
Fu Li, Xingqing Jing, Institute of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-7
The Application of Compact Heat Exchangerin 10MW Nuclear Power Conversion System
Yu Cheng, Jinling Li, Jie Wang, Suyuan Yu, Institute of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-7
Study on The Thermodynamic Cycle of HTR-10GT
Zhiyong Huang, Jie Wang, Jinling Li, Institute of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-13
Concept of Pebble Bed Based HTGR With Fast Pebble Discharge System
Jianling Dong, Suyuan Yu, INET, Beijing, CHINA
HTR-2004, pp:1-7
Design and Experiments of The Active Magnetic Bearing System For The HTR-10
Lei Shi, Lei Zhao, Guojun Yang, Huidong Gu, Xingzhong Diao, Suyuan Yu, Institute of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-16
Design Features of Gas Turbine Power Conversion System for HTR-10GT
Jie Wang, Zhiyong Huang, Shutang Zhu, Suyuan Yu, Institute of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-12
The Monitoring System of The PCU For The 10MW High Temperature Gas-Cooled Reactor
Zhjengang Shi, Meisheng Zha, Hong Peng, Lei Shi, Lei Zhao, Institute of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-15
Using Transfer Function Method To Study The Dynamic Circulation Characteristics of HTR-10GT
Shutang Zhu, Jie Wang, Zhioyong Huang, Suyuan Yu, Institute of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-9
Design of Chinese Modular High-Temperature Gas-Cooled Reactor HTR-PM
Zuoyi Zhang, Zongxin Wu, Yuanhui Xu, Yuliang Sun, Fu Li, Institue of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-8
Dynamics Analysis of Very Flexible Rotor
Yang Xu, Lei Zhao, Suyuan Yu, Institute of Nuclear Energy Technology, Beijing, CHINA
HTR-2004, pp:1-6
Impact Analysis of The Catcher Bearing For The Magnetic Suspending Rotor In HTR10-GT Project
Li Wan, Yang Xu, Guojun Yang, Lei Zhao, Xinxin Wu, Institute of Nuclear Energy Technology, Beijing, CHINA
HTR-2004, pp:1-8
Discussion About Several Key Problems To Develop Helium Gas Turbo Compressor System of HTR-10GT
Limin Xu, Harbin Marine Boiler and Turbine Research Institute, Harbin, CHINA
HTR-2004, pp:1-8
The Full Perfornance Test For The Safety Valves of HTR-10
Xinxin Wu, Jianling Dong, Rizhu Li, Institute of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-10
Design of The HTR-10 Helium Circulator With The Active Magnetic Bearings
Xingzhong Diao, Lei Zhao, Huizhong Zhou Meisheng Zha, Jie Wang, Suyuan Yu, Institute of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-6
Housing Vibration Control of A Large Rotor Suspended By Magnetic Bearings
Kai Zhang, Hongbin Zhao, Department of Engineering Physics, Tsinghua University, Beijing, CHINA; Lei Zhao, Institute of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-8
Redundancy Design and Reliability Analysis of AMB System
Gu Huidong, Zhao Hongbin, Department of Engineering Physics, Tsinghua University, Beijing, CHINA; Lei Zhao, Lei Shi, Xingzhong Diao, Suyuan Yu, Institute of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-8
Fatigue Analysis of Steam Generator In HTR-10
Xiaotian Li, Shuyuan He, Institute of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-6
The Feasibility Study on PCPV In Modular HTR
Shuyuan He, Xinxin Wu, Jisheng Wang, Institute of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-6
Theoretical Analysis On The Tribological Properties Of HTGR-10 Graphite
Xuanyu Sheng, Suyuan Yu, , Institute of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-7
A Flexible Rotor In HTR-10 Passing Through The First Bending Critical Speed 24,000 RPM
Huidong Gu, Hongbin Zhao, Department of Engineering Physics, Tsinghua University, Beijing, CHINA; Lei Zhao, Lei Shi, Xingzhong Diao, Suyuan Yu, , Institute of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-9
Preliminary Scheme Design and Analysis of Catcher Bearing for HTR-10GT
Guojun Yang, Li Wan, Lei Zhao, Suyuan Yu, , Institute of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-8
The Effect of Softening on The Predicted Strength of Brittle Materials Using a Continuum Damage Mechanics Failure Model
Li Shi, Haiyan Li, Suyuan Yu, Institute of Nuclear and New Energy Technology, Beijing, CHINA; S.L. Fok, B.J. Marsden, The Manchester School of Engineering, University of Manchester, Manchester, UNITED KINGDOM
HTR-2004, pp:1-8
The Mode Design Of The Rotor In Active Magnetic Bearing
Hongwei Li, Yang Xu, Lei Zhao, Suyuan Yu, Institute of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-5
HTGR Helium Turbine Conceptual Design By Genetic/Gradient Optimization
Guojun Yang, Suyuan Yu, Long Yang, Zhiyong Huang, Institute of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-5
Leak-Before-Break Analysis Of The HTR-10's Hot-Gas Duct Vessel
Zhengming Zhang, Shuyuan He, Institute of Nuclear and New Energy Technology, Beijing, CHINA
HTR-2004, pp:1-8
Safety Demonstration Tests On HTR-10
Shouyin Hu, Ruipian Wang, Zuying Gao, Institute of Nuclear Energy Technology, Tsinghua University, Beijing, CHINA
HTR-2004, pp:1-16
Power Operation Commissioning Tests Of HTR-10
Shouyin Hu, Ruipian, Wang, Institute of Nuclear Energy Technology, Tsinghua University, Beijing, CHINA
HTR-2004, pp:1-13
China's HTR test module project
Zhong Daxin; Xu Yuanhui; Wu Zongxin (Qinghua Univ., Beijing, BJ (China). Inst. of
Nuclear Energy Technology)
IAEA-TECDOC--784, pp:11-14
High temperature gas cooled reactors in China
He Jiachen; Qian Jihui (Ministry of Nuclear Industry, Beijing, BJ
(China))
IWGGCR--19, pp:35-38
Relevant safety issues in designing the HTR-10 reactor
Y. Sun, Y. Xu (Institute of Nuclear Energy Technology, Beijing, China)
IAEA-TECDOC--1210, pp:35-38
Status of the HTR research and development programme in
China
Xu Yuanhui (Institute of Nuclear Energy Technology, Beijing
(China))
IWGGCR--19, pp:38-42
High temperature process heat application of nuclear energy in China
Wang Dazhong; Xu Yuanhui; Wu Zhongxin; Tong Yunxian; Ju Huaiming (Institute of
Nuclear Energy Technology, Beijing (China))
IAEA-TECDOC--761, pp:42-46
Study on Coupling a Gas Turbine Cycle to the HTR-10 Test Reactor
Y.Sun, Y.Zhang, Y.Xu, Institute of Nuclear Energy technology, Beijing, PR China
IAEA-TECDOC--1238, pp:50-56
The NACOK experiment on natural convection of air through the core
Froehling, W.; Hohn, H.; Kugeler, M. (Forschungszentrum Juelich GmbH (Germany));
Sun, Y.; Zhang, Z. (Institute of Nuclear Energy Technology, Beijing (China))
IAEA-TECDOC--784, pp:55-61
Afterheat removal for HTR-10 test module under accident conditions
Gao Zuying; He Shuyan; Zhang Min (Qinghua Univ., Beijing, BJ (China). Inst.
of Nuclear Energy Technology)
IAEA-TECDOC--757, pp:63-72
Physical status of the 10 MW test module.
Luo Jingyu (Qinghua Univ., Beijing, BJ (China). Inst. of Nuclear
Energy Technology)
IWGGCR--24, pp:66-72
Transient analysis of air ingress from broken pipe into the HTR-10 reactor pressure vessel
Gao Zuying; Li Baoyan; Wang Chunyun; Jiang Zhiqiang (Qinghua Univ., Beijing, BJ
(China). Inst. of Nuclear Energy Technology)
IAEA-TECDOC--784, pp:69-72
Design precautions for coupling interfaces between nuclear heating reactor and heating grid or
desalination plant
Zheng Wenxiang (Institute of Nuclear Energy Technology (INET), Tsinghua University,
Beijing (China))
IAEA-TECDOC--1056, pp:85-89
Transient analysis of water ingress into the HTR-10 high temperature gas cooled test reactor
Gao Zuying; Wang Chunyun (Qinghua Univ., Beijing, BJ (China). Inst. of Nuclear Energy
Technology)
IAEA-TECDOC--784, pp:92-96
Study of reaction: Coated SiC coating on HTGR fuel elements
Tang Chunhe; Guan Jie; Li Ende; Zhang Chun (Qinghua Univ., Beijing, BJ (China). Inst. of
Nuclear Energy Technology)
IAEA-TECDOC--784, pp:107-109
Study of the method to improve the corrosion resistance of the matrix materials of spherical fuel elements in HTGR
Zhang Shichao; Qiu Xueliang; Ma Changwen (Qinghua Univ., Beijing, BJ (China). Inst. of
Nuclear Energy Technology)
IAEA-TECDOC--784, pp:116-120
Analysis of stress in reactor core vessel under effect of pressure lose shock wave
L. Yong, L. Baoting (Institute of Nuclear Energy Technology Tsinghua University, Beijing)
IAEA-TECDOC--1210, pp:181-185
Nuclear reactor development in China for non-electrical applications
Sun Yuliang; Zhong Daxin; Dong Duo; Xu Yuanhui (Institute of Nuclear Energy
Technology, Tsinghua University, Beijing (China))
IAEA-TECDOC--1056, pp:201-208
The HTR-10 test reactor project and potential use of HTGR for non-electric application in China
Sun Yuliang; Zhong Daxin; Xu Yuanhui; Wu Zhongxin (Institute of Nuclear
Energy Technology, Beijing (China))
IAEA-TECDOC--923, pp:211-222
Chinese development of water-cooled reactors for non-electric applications
Sun Yuliang; Duo Dong (Institute of Nuclear Energy Technology, Beijing
(China))
IAEA-TECDOC--923, pp:223-229
Techno-economic analysis of seawater desalination using high temperature gas-cooled reactor
L. Wu, Z. Qin (Tsinghua University, Beijing, China)
IAEA-TECDOC--1210, pp:223-228
Analysis of the nuclear heating reactor and its possible application in seawater desalination
Zhang Yajun; Zhang Dafang; Dong Duo (Institute of Nuclear Energy Technology, Tsinghua
University, Beijing (China))
IAEA-TECDOC--1056, pp:235-242
Experiments on safety features and comprehensive applications of the 5 MW nuclear heating reactor
Zhang Dafang; Dong Duo (Institute of Nuclear Energy Technology, Tsinghua University,
Beijing (China))
IAEA-TECDOC--1056, pp:339-357
Present status of research and development for HTR in China
Wang Dazhong; Zhong Daxin; Xu Yuanhul (Institute of Nuclear Energy Technology, Tsinghua University, Beijing (China))
IAEA-TC--389.26, pp:652-667
The prospects of HTR plant in China
Ye Liangcheng
IAEA-TC--389.26, pp:668-674
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