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Dynamic simulation of a space gas-cooled reactor power system with a closed Brayton cycle
Frontiers in Energy 2021, Volume 15, Issue 4, Pages 916-929 doi: 10.1007/s11708-021-0757-9
Keywords: gas-cooled space nuclear reactor power closed Brayton cycle system startup and shutdown positive reactivity
Zuoyi Zhang, Yujie Dong, Fu Li, Zhengming Zhang, Haitao Wang, Xiaojin Huang, Hong Li, Bing Liu, Xinxin Wu, Hong Wang, Xingzhong Diao, Haiquan Zhang, Jinhua Wang
Engineering 2016, Volume 2, Issue 1, Pages 112-118 doi: 10.1016/J.ENG.2016.01.020
Keywords: Nuclear energy High-temperature gas-cooled reactor Pebble bed Modular high-temperature gas-cooled reactor High-temperature gas-cooled reactor pebble-bed module
Nuclear Hydrogen Production Based on High Temperature Gas Cooled Reactor in China
Zhang Ping, Xu Jingming, Shi Lei, Zhang Zuoyi
Strategic Study of CAE 2019, Volume 21, Issue 1, Pages 20-28 doi: 10.15302/J-SSCAE-2019.01.004
Nuclear hydrogen production is one of the most prospective approachesfor efficient, massive and CO2-free hydrogen production, while the high temperature gas cooled reactor(HTGR) which has been intensively developed in China is considered as the most suitable reactor typefor nuclear hydrogen production.In addition, the potential technologies for coupling to the reactor are discussed, and the industrial
Keywords: high temperature gas cooled reactor nuclear hydrogen production thermochemical cycle high temperature
An old issue and a new challenge for nuclear reactor safety
F. D’AURIA
Frontiers in Energy 2021, Volume 15, Issue 4, Pages 854-859 doi: 10.1007/s11708-021-0729-0
Keywords: large break loss of coolant accident (LBLOCA) nuclear reactor safety (NRS) licensing perspectives basisfor design of water cooled nuclear reactors (WCNR)
Development Strategy of High Temperature Gas Cooled Reactor in China
Zhang Zuoyi, Wu Zongxin, Wang Dazhong, Tong Jiejuan
Strategic Study of CAE 2019, Volume 21, Issue 1, Pages 12-19 doi: 10.15302/J-SSCAE-2019.01.003
High temperature gas cooled reactor (HTGR) together with its successor, the very high temperature reactor, is one of the six nuclear energy systems identified and selectedin the past years, and now is in the front-runner status with respect to the commercial-level HTGR nuclearpower plant.
Keywords: high temperature gas cooled reactor very high temperature technology road map
Advanced Reactor Types and China’s Nuclear Power Industry
Hu Yalei
Strategic Study of CAE 2005, Volume 7, Issue 11, Pages 98-102
This article describes the four generation of reactor types.Firstly, it looks back the development of the 1st. and 2nd. generation reactor types; Secondly, explainsthe development and the design characteristics of several typical 3rd generation advanced reactor typesFinally, it introduces the related situation in China's nuclear power industry.
Keywords: advanced reactor types China’s nuclear power industry
A numerical study of helium-heated inorganic membrane reformer coupling to HTGR
YIN Huaqiang, JIANG Shengyao, JU Huaiming, ZHANG Youjie
Frontiers in Energy 2007, Volume 1, Issue 4, Pages 446-450 doi: 10.1007/s11708-007-0065-3
Keywords: temperature gas-cooled one-dimensional quasi-homogeneous steady-state helium-heated
A perspective of “Nuclear Hot Spring” for long-term sustainable economy of the world
Yingzhong LU
Frontiers in Energy 2011, Volume 5, Issue 4, Pages 349-357 doi: 10.1007/s11708-011-0168-4
Keywords: natural safety reactor full power natural circulation sustainable world economy
Corrosion mechanisms of candidate structural materials for supercritical water-cooled reactor
Lefu ZHANG, Fawen ZHU, Rui TANG
Frontiers in Energy 2009, Volume 3, Issue 2, Pages 233-240 doi: 10.1007/s11708-009-0024-y
Keywords: supercritical water-cooled reactor general corrosion oxide film corrosion mechanism
Preliminary design of an SCO conversion system applied to the sodium cooled fast reactor
Frontiers in Energy 2021, Volume 15, Issue 4, Pages 832-841 doi: 10.1007/s11708-021-0777-5
Keywords: sodium-cooled fast reactor (SFR) supercritical carbon dioxide (SCO2) brayton cycle load
Mao Xiaoming
Strategic Study of CAE 2012, Volume 14, Issue 8, Pages 14-16
As China's nuclear industry flagship in developing overseas nuclear, with project development as its engine, makes unremitting efforts in the development of 1 000 MWe nuclearpower plants, nuclear research reactors, In hospital nuclear irradiation and modular small type reactor, and contributes to the peaceful use of nuclear energy and technology.
Keywords: 1 000 MW nuclear power plant nuclear research reactor in hospital nuclear irradiation modular smalltype reactor
Third Qinshan Nuclear Power Co. Ltd, CNNC
Strategic Study of CAE 2008, Volume 10, Issue 3, Pages 73-86
Qinshan Phase III (PHWR) Nuclear Power Plant, the first commercial heavy water reactor nuclear powerAs the owner, the Third Qinshan Nuclear Power Company (TQNPC) persisted in independent innovation managementThe project construction practice has helped China’s nuclear power project management to becomepower plant and nuclear power qinshan joint venture company, the improvement and developemnt of nuclearpower project management level in Qinshan Phase III (PHWR) nuclear power plant provided reference for
Keywords: Qinshan Phase III heavy water reactor nuclear power plant project construction technical innovation
Studies on advanced water-cooled reactors beyond generation III for power generation
CHENG Xu
Frontiers in Energy 2007, Volume 1, Issue 2, Pages 141-149 doi: 10.1007/s11708-007-0018-6
Keywords: Chinese situation selection generation water-cooled feasibility
The Status of the US High-Temperature Gas Reactors Review
Andrew C. Kadak
Engineering 2016, Volume 2, Issue 1, Pages 119-123 doi: 10.1016/J.ENG.2016.01.026
Keywords: High temperature gas reactor Next-Generation Nuclear Plant (NGNP) Licensing Nuclear Regulatory Commission
Overall Development Strategy of China’s New-Generation Nuclear Fuel
Li Guanxing, Zhou Bangxin, Xiao Min, Jiao Yongjun, Ren Zhongming
Strategic Study of CAE 2019, Volume 21, Issue 1, Pages 6-11 doi: 10.15302/J-SSCAE-2019.01.002
Keywords: nuclear fuel nuclear materials light water reactor pressurized water reactor fast reactor nuclear fuel
Title Author Date Type Operation
Dynamic simulation of a space gas-cooled reactor power system with a closed Brayton cycle
Journal Article
The Shandong Shidao Bay 200 MWe High-Temperature Gas-Cooled Reactor Pebble-Bed Module (HTR-PM) Demonstration Power Plant: An Engineering and Technological Innovation
Zuoyi Zhang, Yujie Dong, Fu Li, Zhengming Zhang, Haitao Wang, Xiaojin Huang, Hong Li, Bing Liu, Xinxin Wu, Hong Wang, Xingzhong Diao, Haiquan Zhang, Jinhua Wang
Journal Article
Nuclear Hydrogen Production Based on High Temperature Gas Cooled Reactor in China
Zhang Ping, Xu Jingming, Shi Lei, Zhang Zuoyi
Journal Article
Development Strategy of High Temperature Gas Cooled Reactor in China
Zhang Zuoyi, Wu Zongxin, Wang Dazhong, Tong Jiejuan
Journal Article
A numerical study of helium-heated inorganic membrane reformer coupling to HTGR
YIN Huaqiang, JIANG Shengyao, JU Huaiming, ZHANG Youjie
Journal Article
A perspective of “Nuclear Hot Spring” for long-term sustainable economy of the world
Yingzhong LU
Journal Article
Corrosion mechanisms of candidate structural materials for supercritical water-cooled reactor
Lefu ZHANG, Fawen ZHU, Rui TANG
Journal Article
Preliminary design of an SCO conversion system applied to the sodium cooled fast reactor
Journal Article
Igniting the engine, devoting to project development——outline of project development in nuclear energy
Mao Xiaoming
Journal Article
Project Construction and Important Technical Innovation for Qinshan Phase III (PHWR) Nuclear Power Plant
Third Qinshan Nuclear Power Co. Ltd, CNNC
Journal Article
Studies on advanced water-cooled reactors beyond generation III for power generation
CHENG Xu
Journal Article