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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
Keywords: large break loss of coolant accident (LBLOCA) nuclear reactor safety (NRS) licensing perspectives basisfor design of water cooled nuclear reactors (WCNR)
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
Experience gained in analyzing severe accidents for WWER RP using CC SOCRAT
Frontiers in Energy 2021, Volume 15, Issue 4, Pages 872-886 doi: 10.1007/s11708-021-0796-2
Keywords: system of codes for realistic analysis of severe accidents (SOCRAT) design basis accidents (DBAs) severeaccidents (SAs) computer code (CC) nuclear power plant (NPP) design water-cooled water-moderated
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
Development Status and Prospect of Marine Nuclear Power Equipment in China and Abroad
Zheng Jie,Yu Fan,Zhu Junmin,Liu Cungen, Wang Xinyue,Zhu Yingfu
Strategic Study of CAE 2023, Volume 25, Issue 3, Pages 62-73 doi: 10.15302/J-SSCAE-2023.03.007
Marine nuclear power equipment (MNPE) is crucial for the sustainablecivil use and from land to sea, and its main technical source is compact and integrated pressurized waterreactors.In the near future, the equipment types of MNPE will focus on offshore floating nuclear power plantsand nuclear-powered icebreakers.
Keywords: marine nuclear power equipment small modular reactors pressurized water reactors nuclear power ships offshore floating nuclear power plants
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
Overall Development Strategy of Materials Used for China’s New-Generation Nuclear Power Plants
Gan Yong, Zhao Xiangeng, Xu Kuangdi
Strategic Study of CAE 2019, Volume 21, Issue 1, Pages 1-5 doi: 10.15302/J-SSCAE-2019.01.001
Keywords: new-generation nuclear power plants pressurized water reactors materials used for nuclear power plants
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) which has been intensively developed in China is considered as the most suitable reactor type for nuclearwater-splitting process, the hybrid sulfur process, as well as the high temperature steam electrolysisThe progress of the nuclear hydrogen production technologies both in the world and China are shortly
Keywords: high temperature gas cooled reactor nuclear hydrogen production thermochemical cycle high temperature
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
Core designing of a new type of TVS-2M FAs: neutronics and thermal-hydraulics design basis limits
Saeed GHAEMI, Farshad FAGHIHI
Frontiers in Energy 2021, Volume 15, Issue 1, Pages 256-278 doi: 10.1007/s11708-018-0583-x
Keywords: TVS-2M FAs core design basis limits VVER-1000 analysis mixture of uranium-gadolinium oxides fuels thermal-hydraulics
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
Keywords: supercritical water cooled reactor tensile impact toughness corrosion aging
Are Small Reactors Nuclear Power’s Next Big Thing?
Mitch Leslie
Engineering 2020, Volume 6, Issue 3, Pages 210-212 doi: 10.1016/j.eng.2020.01.003
The development on seismic design and evaluation of CGNPC after Fukushima accident
Mao Qing,Wu Yingxi,Zhang Jian,Meng Ajun,Zhang Tao,Yang Chunju,Liu Fang
Strategic Study of CAE 2013, Volume 15, Issue 4, Pages 46-51
This paper introduced the seismic design requirements of nuclear powerplant, the seismic design situation of the unit in construction or in service, and the serious consequencethe improvement taken by China Guangdong Nuclear Power Holding Co.Finally, this paper presented some steps for the new nuclear power plants at the seismic design and evaluationto enhance the seismic capacity of nuclear power plants through technical means.
Keywords: seismic design basis beyond design basis earthquake seismic margin assessment(SMA) seismic isolation
Zulkifly JEMAAT,Josep Anton TORA,Albert BARTROLI,Julián CARRERA,Julio PEREZ
Frontiers of Environmental Science & Engineering 2015, Volume 9, Issue 3, Pages 528-533 doi: 10.1007/s11783-014-0641-5
Keywords: partial nitrification reject water high strength ammonium wastewater closed-loop control
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
Studies on advanced water-cooled reactors beyond generation III for power generation
CHENG Xu
Journal Article
Dynamic simulation of a space gas-cooled reactor power system with a closed Brayton cycle
Journal Article
Development Status and Prospect of Marine Nuclear Power Equipment in China and Abroad
Zheng Jie,Yu Fan,Zhu Junmin,Liu Cungen, Wang Xinyue,Zhu Yingfu
Journal Article
Corrosion mechanisms of candidate structural materials for supercritical water-cooled reactor
Lefu ZHANG, Fawen ZHU, Rui TANG
Journal Article
Overall Development Strategy of Materials Used for China’s New-Generation Nuclear Power Plants
Gan Yong, Zhao Xiangeng, Xu Kuangdi
Journal Article
Nuclear Hydrogen Production Based on High Temperature Gas Cooled Reactor in China
Zhang Ping, Xu Jingming, Shi Lei, Zhang Zuoyi
Journal Article
Preliminary design of an SCO conversion system applied to the sodium cooled fast reactor
Journal Article
Core designing of a new type of TVS-2M FAs: neutronics and thermal-hydraulics design basis limits
Saeed GHAEMI, Farshad FAGHIHI
Journal Article
Feasibility analysis of modified AL-6XN steel for structure component application in supercritical water-cooled
Xinggang LI, Qingzhi YAN, Rong MA, Haoqiang WANG, Changchun GE
Journal Article
The development on seismic design and evaluation of CGNPC after Fukushima accident
Mao Qing,Wu Yingxi,Zhang Jian,Meng Ajun,Zhang Tao,Yang Chunju,Liu Fang
Journal Article
Achievement of high rate nitritation with aerobic granular sludge reactors enhanced by sludge recirculation
Zulkifly JEMAAT,Josep Anton TORA,Albert BARTROLI,Julián CARRERA,Julio PEREZ
Journal Article