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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: supercritical carbon dioxide (SCO2) Brayton cycle has become an ideal power conversion system for sodium-cooledfast reactors (SFR) due to its high efficiency, compactness, and avoidance of sodium-water reaction., and the sodium circuit temperature and the heat load are the operating boundaries of the cycle systemdioxide heat exchanger sodium side outlet temperature unchanged, the inter-stage cooling recompressioncycle can match the operation of the SFR very well.

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

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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)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.When the GCR is shut down in an emergency, the residual heat of the reactor can be removed through theThis 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    

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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 production

Keywords： supercritical water-cooled reactor     general corrosion     oxide film     corrosion mechanism    

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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 cooled

Keywords： large break loss of coolant accident (LBLOCA)     nuclear reactor safety (NRS)     licensing perspectives     basisfor design of water cooled nuclear reactors (WCNR)    

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The Status and Prospects of Fast Reactor Technology Development in China

Xu Mi

Strategic Study of CAE 2008, Volume 10, Issue 1,   Pages 70-76

Abstract: GWe and 240 GWe in 2030 and 2050 respectively.The basic strategy of PWR-FBR matched development with fastreactor metal fuel closed cycle for a sustainable and quick increasing nuclear energy supply is adopted.Anotherand ADS.The fast reactor engineering development will be divided into three steps: China Experimentalfast Reactor(CEFR 65 MWt/20 MWe), China Prototype/Demon_stration Fast Reactor(CPFR/CDFR≥1 500 MWt/600 MWe)and China Demonstration Fast Breeder Reactor(CDFBR100～1 500 MWe).The CEFR is under installation

Keywords： fast reactor development strategy     breeder     burner     China experimental fast reactor    

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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 selected

Keywords： high temperature gas cooled reactor     very high temperature     technology road map    

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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: approaches for efficient, massive and CO2-free hydrogen production, while the high temperature gas cooledreactor (HTGR) which has been intensively developed in China is considered as the most suitable reactorIn 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    

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Feasibility analysis of modified AL-6XN steel for structure component application in supercritical water-cooledreactor

Xinggang LI, Qingzhi YAN, Rong MA, Haoqiang WANG, Changchun GE

Frontiers in Energy 2009, Volume 3, Issue 2,   Pages 193-197 doi: 10.1007/s11708-009-0030-0

Abstract: qualification of modified AL-6XN steel as an in-core component and cladding material in a supercritical water-cooledreactor.as one of the candidate materials for in-core components and cladding tubes in supercritical water-cooled

Keywords： supercritical water cooled reactor     tensile     impact toughness     corrosion     aging    

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The Shandong Shidao Bay 200 MWe High-Temperature Gas-Cooled Reactor Pebble-Bed Module (HTR-PM 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: December 9, 2012 at the Shidao Bay site in Rongcheng, Shandong Province, China, the construction of the reactorbuilding for the world’s first high-temperature gas-cooled reactor pebble-bed module (HTR-PM)The thermal power of a single HTR-PM reactor module is 250 MWth, the helium temperatures atthe reactor core inlet/outlet are 250/750 °C, and a steam of 13.25 MPa/567 °C is produced atTwo HTR-PM reactor modules are connected to a steam turbine to form a 210 MWe nuclear power

Keywords： Nuclear energy     High-temperature gas-cooled reactor     Pebble bed     Modular high-temperature gas-cooled reactor     High-temperature gas-cooled reactor pebble-bed module    

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The Lead Fast Reactor: An Opportunity for the Future? Vies & Comments

Alessandro Alemberti

Engineering 2016, Volume 2, Issue 1,   Pages 59-62 doi: 10.1016/J.ENG.2016.01.022

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A Preliminary Study of a Sustainable Energy System Based on Fast Reactor in China

Yang Yong,Wang Jing and Xu Mi

Strategic Study of CAE 2018, Volume 20, Issue 3,   Pages 32-38 doi: 10.15302/J-SSCAE-2018.03.005

Abstract: According to studies, the closed fuel cycle based on the fast reactor can effectively breed the nuclearAccording to the three-stage strategy of "experimental reactor–demonstration reactor–commercial reactor" of the fast reactor in China, as well as the situation that nuclear powerdevelopment started late in China, a road map is suggested for the development of the fast reactor inChina, in which the main mission for the fast reactor is to breed nuclear fuels till 2050, and to burn

Keywords： fast breeder reactor     sustainable nuclear energy system     proliferation and transmutation    

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Experimental study of critical flow of water at supercritical pressure

Yuzhou CHEN, Chunsheng YANG, Shuming ZHANG, Minfu ZHAO, Kaiwen DU, Xu CHENG

Frontiers in Energy 2009, Volume 3, Issue 2,   Pages 175-180 doi: 10.1007/s11708-009-0029-6

Abstract: predictions of the homogeneous equilibrium model, the Bernoulli correlation, and the models used in the reactor

Keywords： critical flow     supercritical water-cooled reactor(SCWR)     reactor safety     loss of coolant accident(LOCA)    

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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 cycleThis paper puts forward suggestions on the development of nuclear fuels and materials for PWRs, fast

Keywords： nuclear fuel     nuclear materials     light water reactor     pressurized water reactor     fast reactor     nuclear fuel    

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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 advanced reactorThe paper discusses some main criteria for the selection of future water-cooled reactors by consideringBased on the suggested selection criteria, two new types of water-cooled reactors are recommended forThe 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    

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Alumina modified sodium vanadate cathode for aqueous zinc-ion batteries

Frontiers in Energy   Pages 775-781 doi: 10.1007/s11708-023-0902-8

Abstract: Therefore, sodium vanadate Na2V6O16·3H2O (NVO) was chosen

Keywords： cathodes     aqueous zinc-ion batteries     sodium vanadate     alumina     coating    

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Title Author Date Type Operation

Preliminary design of an SCO conversion system applied to the sodium cooled fast reactor

Journal Article

Dynamic simulation of a space gas-cooled reactor power system with a closed Brayton cycle

Journal Article

Corrosion mechanisms of candidate structural materials for supercritical water-cooled reactor

Lefu ZHANG, Fawen ZHU, Rui TANG

Journal Article

An old issue and a new challenge for nuclear reactor safety

F. D’AURIA

Journal Article

The Status and Prospects of Fast Reactor Technology Development in China

Xu Mi

Journal Article

Development Strategy of High Temperature Gas Cooled Reactor in China

Zhang Zuoyi, Wu Zongxin, Wang Dazhong, Tong Jiejuan

Journal Article

Nuclear Hydrogen Production Based on High Temperature Gas Cooled Reactor in China

Zhang Ping, Xu Jingming, Shi Lei, Zhang Zuoyi

Journal Article

Feasibility analysis of modified AL-6XN steel for structure component application in supercritical water-cooledreactor

Xinggang LI, Qingzhi YAN, Rong MA, Haoqiang WANG, Changchun GE

Journal Article

The Shandong Shidao Bay 200 MWe High-Temperature Gas-Cooled Reactor Pebble-Bed Module (HTR-PM

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

The Lead Fast Reactor: An Opportunity for the Future?

Alessandro Alemberti

Journal Article

A Preliminary Study of a Sustainable Energy System Based on Fast Reactor in China

Yang Yong,Wang Jing and Xu Mi

Journal Article

Experimental study of critical flow of water at supercritical pressure

Yuzhou CHEN, Chunsheng YANG, Shuming ZHANG, Minfu ZHAO, Kaiwen DU, Xu CHENG

Journal Article

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

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

Journal Article

Studies on advanced water-cooled reactors beyond generation III for power generation

CHENG Xu

Journal Article

Alumina modified sodium vanadate cathode for aqueous zinc-ion batteries

Journal Article