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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: are based on, among the other things, long lasting research and operational experience in the area of watercooled nuclear reactors (WCNR).of coolant accident (LBLOCA) has been, so far, the orienting scenario within AA and a basis for the designof reactors.few years is as follows: Progress in fundamentals was stagnant, namely in those countries where the WCNR

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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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: The 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 fuelassembly design (two-rows FA) are proposed.

Keywords： Chinese situation     selection     generation     water-cooled     feasibility    

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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

Abstract: The current Russian regulatory documents on the safety of nuclear power plant (NPP) specify the requirementsregarding design basis accidents (DBAs) and beyond design basis accidents (BDBAs), including severethe reactor lower plenum (HEFEST)) was developed in Russia to analyze a wide range of SAs at NPP with water-cooledwater-moderated power-generating reactor (WWER) at all stages of the accident.the code and broadening of its applicability are continually being pursued by the code developers (Nuclear

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    

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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, transientThis 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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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

Abstract:

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    

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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: are presently considered to be the candidate structural or fuel-cladding materials for supercritical water-cooledcorrosion cracking of these candidate alloys still remain to be a major problem in the selection of nuclearfuel cladding and other structural materials, such as water rod.materials exhibits quite complicated mechanism in high-temperature and high-pressure supercritical water

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

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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

Abstract: Among the 56 nuclear power plants in service or under construction, 52 nuclear power plants adopt pressurizedwater reactors.Demonstration power plants are being built for the high temperature gas cooled reactor and the sodiumcold fast reactor, and other reactor types such as molten salt reactors, accelerator-driven subcriticalsystems, and supercritical water reactors are still in the research stage.

Keywords： new-generation nuclear power plants     pressurized water reactors     materials used for nuclear power plants    

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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:

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    

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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: 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.The analysis shows that when the nuclear island adopts the flow-advanced operation strategy and the carbon

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

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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

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-cooledconsidered as one of the candidate materials for in-core components and cladding tubes in supercritical water-cooledreactors.

Keywords： supercritical water cooled reactor     tensile     impact toughness     corrosion     aging    

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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

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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

Frontiers of Environmental Science & Engineering 2015, Volume 9, Issue 3,   Pages 528-533 doi: 10.1007/s11783-014-0641-5

Abstract: ) and the total ammonia nitrogen (TAN) concentrations in the bulk liquid of aerobic granular sludge reactorsHigh strength synthetic wastewaters and reject water were tested with similar performance.Granular sludge and nitritation were stable in the long term continuous operation of the reactors.

Keywords： partial nitrification     reject water     high strength ammonium wastewater     closed-loop control    

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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: text-align: justify;">This study analyzed the worldwide status of and development trends in pressurized waterPWR 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, fastreactors, and nuclear fuel cycles in China.

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

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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: Experimental studies of the critical flow of water were conducted under steady-state conditions with

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

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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: Province, China, the construction of the reactor building for the world’s first high-temperature gas-cooledTwo 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    

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Title Author Date Type Operation

An old issue and a new challenge for nuclear reactor safety

F. D’AURIA

Journal Article

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

CHENG Xu

Journal Article

Experience gained in analyzing severe accidents for WWER RP using CC SOCRAT

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

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

Are Small Reactors Nuclear Power’s Next Big Thing?

Mitch Leslie

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

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

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

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

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