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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

Abstract: Space nuclear reactor power (SNRP) using a gas-cooled reactor (GCR) and a closed Brayton cycle (CBC)is the ideal choice for future high-power space missions.To investigate the safety characteristics and develop the control strategies for gas-cooled SNRP, transientThe system finally has the ability to achieve a new steady-state with a higher reactor power.This paper may provide valuable references for safety design and analysis of the gas-cooled SNRP coupled

Keywords: gas-cooled space nuclear reactor power     closed Brayton cycle     system startup and shutdown     positive reactivity    

The Shandong Shidao Bay 200 MWe High-Temperature Gas-Cooled Reactor Pebble-Bed Module (HTR-PM) Demonstration Power Plant: An Engineering and Technological Innovation Review

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

Abstract: building for the world’s first high-temperature gas-cooled reactor pebble-bed module (HTR-PM)demonstration power plant was completed in June, 2015.The thermal power of a single HTR-PM reactor module is 250 MWth, the helium temperatures atTwo HTR-PM reactor modules are connected to a steam turbine to form a 210 MWe nuclear powerand balancing safety and economics; these obtained experiences may also be referenced by the global nuclear

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

Abstract:

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

Abstract: Nuclear reactor safety (NRS) and the branch accident analysis (AA) constitute proven technologies: thesebased on, among the other things, long lasting research and operational experience in the area of water coolednuclear reactors (WCNR).Weaknesses became evident, noticeably in relation to nuclear fuel under high burn-up.

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

Abstract:

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

Abstract:

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

Abstract: computer program were developed for helium-heated inorganic membrane reformer coupling to high temperature gas-cooledreactor (HTGR).

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

Abstract: The nuclear fission (and fusion later), however, could release huge amount of energy to create sufficientresources and turn the said pessimistic modelinto a new optimistic “Sustainable World Model”.The dilemma of nuclearThe proposed full-power natural circulation “Nuclear Hot Spring (NHS)” reactor could operate solely onThe cheap, unlimited supply of energy from nuclear energy could change the geopolitics forever, and finally

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

Abstract: presently considered to be the candidate structural or fuel-cladding materials for supercritical water-cooledreactor (SCWR), one of the promising generation IV reactor for large-scale electric power productioncorrosion cracking of these candidate alloys still remain to be a major problem in the selection of nuclear

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

Abstract: The supercritical carbon dioxide (SCO2) Brayton cycle has become an ideal power conversionsystem for sodium-cooled fast reactors (SFR) due to its high efficiency, compactness, and avoidanceThen, based on the developed system transient analysis program (FR-Sdaso), a pool-type SFR power plantThe analysis shows that when the nuclear island adopts the flow-advanced operation strategy and the carbondioxide flowrate in the SCO2 power conversion system is adjusted with the goal of maintaining

Keywords: sodium-cooled fast reactor (SFR)     supercritical carbon dioxide (SCO2)     brayton cycle     load    

Igniting the engine, devoting to project development——outline of project development in nuclear energy

Mao Xiaoming

Strategic Study of CAE 2012, Volume 14, Issue 8,   Pages 14-16

Abstract:

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    

Project Construction and Important Technical Innovation for Qinshan Phase III (PHWR) Nuclear Power Plant

Third Qinshan Nuclear Power Co. Ltd, CNNC

Strategic Study of CAE 2008, Volume 10, Issue 3,   Pages 73-86

Abstract:

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

Abstract: China s ambitious nuclear power program motivates the country s nuclear community to develop advancednuclear power.future Chinese nuclear power generation.The supercritical water-cooled reactor has favorable features in economics, sustainability and technologyA new supercritical water-cooled reactor (SCWR) core structure (the mixed reactor core) and a new fuel

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

Abstract: the Energy Policy Act of 2005 mandating the construction and operation of a high-temperature gasreactor (HTGR) by 2021.This law was passed after a multiyear study by national experts on what future nuclear technologies shouldAs a result of the Act, the US Congress chose to develop the so-called Next-Generation Nuclear Plant,government funding requirements for research, unrealistically high temperature requirements for the reactor

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

Abstract: : justify;">This study analyzed the worldwide status of and development trends in pressurized water reactor(PWR) fuel and material technology, fast reactor and other advanced reactor fuel technology, and materialPWR has been the dominant reactor type for nuclear power generation and energy structure transformationChina's fast reactor and fast reactor nuclear fuel development as well as its nuclear fuel cyclereactors, and nuclear fuel cycles in China.

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

An old issue and a new challenge for nuclear reactor safety

F. D’AURIA

Journal Article

Development Strategy of High Temperature Gas Cooled Reactor in China

Zhang Zuoyi, Wu Zongxin, Wang Dazhong, Tong Jiejuan

Journal Article

Advanced Reactor Types and China’s Nuclear Power Industry

Hu Yalei

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

The Status of the US High-Temperature Gas Reactors

Andrew C. Kadak

Journal Article

Overall Development Strategy of China’s New-Generation Nuclear Fuel

Li Guanxing, Zhou Bangxin, Xiao Min, Jiao Yongjun, Ren Zhongming

Journal Article