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Influence evaluation of loading conditions during pressurized thermal shock transients based on thermal-hydraulics

Jinya KATSUYAMA, Shumpei UNO, Tadashi WATANABE, Yinsheng LI

Frontiers of Mechanical Engineering 2018, Volume 13, Issue 4,   Pages 563-570 doi: 10.1007/s11465-018-0487-9

Abstract:

The thermal hydraulic (TH) behavior of coo-lant water is a key factor in the structural integrityassessments on reactor pressure vessels (RPVs) of pressurized water reactors (PWRs) under pressurizedaction time considerably influence various parameters, such as the temperature and flow rate of coolant water

Keywords： structural integrity     reactor pressure vessel     pressurized thermal shock     thermal hydraulic analysis     pressurizedwater reactor     weld residual stress    

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The Formation of the Improved Chinese Pressurized Water Reactor Technology—CPR1000

Pu Jilong

Strategic Study of CAE 2008, Volume 10, Issue 3,   Pages 54-57

Abstract:

This paper introduces the formation of the Improved Chinese PWR technology—CPR1000 which is applied in Ling Ao Nuclear Power Station (Phase II) and Liaoning Hongyanhe Nuclear Power Station, and its key technological innovations.

Keywords： pressurized water reactor     CPR1000     self-owned brand    

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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: style="text-align: justify;">This study analyzed the worldwide status of and development trends in pressurizedwater reactor (PWR) fuel and material technology, fast reactor and other advanced reactor fuel technologyPWR 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 cycle

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

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In-Vessel Melt Retention of Pressurized Water Reactors: Historical Review and Future Research Needs Review

Weimin Ma, Yidan Yuan, Bal Raj Sehgal

Engineering 2016, Volume 2, Issue 1,   Pages 103-111 doi: 10.1016/J.ENG.2016.01.019

Abstract: (IVR) is given, which is a severe accident mitigation measure extensively applied in Generation III pressurizedwater reactors (PWRs).The idea of IVR actually originated from the back-fitting of the Generation II reactor Loviisa VVER-440evolution, the heat fluxes imposed on the vessel by the molten core, and the external cooling of the reactor

Keywords： Pressurized water reactor     Severe accident     In-vessel melt retention     Debris formation     Debris remelting    

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HPR1000: Advanced Pressurized Water Reactor with Active and Passive Safety Review

Ji Xing, Daiyong Song, Yuxiang Wu

Engineering 2016, Volume 2, Issue 1,   Pages 79-87 doi: 10.1016/J.ENG.2016.01.017

Abstract: On one hand, it is an evolutionary design based on proven technology of the existing pressurized waterreactor NPP; on the other hand, it incorporates advanced design features including a 177-fuel-assemblyexperiments and tests have been performed for critical innovative improvements on passive systems, the reactorThe design of HPR1000 fulfills the international utility requirements for advanced light water reactors

Keywords： HPR1000     Active and passive safety     Advanced nuclear power reactor    

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CFD Simulation of thermal hydraulic characteristics in a typical upper plenum of RPV

Mingjun WANG, Lianfa WANG, Yingjie WANG, Wenxi TIAN, Jian DENG, Guanghui SU, Suizheng QIU

Frontiers in Energy 2021, Volume 15, Issue 4,   Pages 930-945 doi: 10.1007/s11708-021-0728-1

Abstract: comparative computational fluid dynamics (CFD) study was conducted on the three different types of pressurizedwater reactor (PWR) upper plenum, named TYPE 1 (support columns (SCs) and control rod guide tubes (CRGTscollected, simplified, and adopted into the BORA facility, which is a 1/5 scale system of the four-loop PWR reactorAfter that, an unsteady calculation to simulate the reactor balance operation at hot full power scenario

Keywords： pressurized water reactor (PWR)     upper plenum     internal structures     temperature distribution     computational    

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Non-pressurized Heating Reactor——a Realizable And Economical Clean Energy

Tian Jiafu

Strategic Study of CAE 2000, Volume 2, Issue 2,   Pages 74-76

Abstract: A non-pressurized heating reactor has been designed based on experience of pool type research reactors

Keywords： atmospheric pollution     greenhouse gas     nuclear heating    

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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: theseare based on, among the other things, long lasting research and operational experience in the area of water

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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Discussions and practice of pressurized water injection for ultra low permeability oilfield

Zhang Hongliang

Strategic Study of CAE 2012, Volume 14, Issue 4,   Pages 62-64

Abstract: Note that first waterflood in such formation where water contained capability is poor and it's difficultto recovery oil efficiently, this paper describes pilot studies of pressurized water injection on singleWater injection front drive and spread area increases or decreases, following changes of pressure ofwater injection.Pressurized water injection can increase coefficient of water injection front drive and enhance oil recovery

Keywords： pressurized waterflood     passive microseismic     ultra low permeable oilfield     affected coefficient     effective    

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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 withpredictions 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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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-cooledreactor (SCWR), one of the promising generation IV reactor for large-scale electric power productionbe a major problem in the selection of nuclear fuel cladding and other structural materials, such as watermaterials 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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Degradation of endocrine disruptor bisphenol A in drinking water by ozone oxidation

XU Bin, GAO Naiyun, RUI Min, WANG Hong, WU Haihui

Frontiers of Environmental Science & Engineering 2007, Volume 1, Issue 3,   Pages 350-356 doi: 10.1007/s11783-007-0060-y

Abstract: The ozone oxidation of endocrine disruptor bisphenol A in drinking water was investigated.A stainless completely mixed reactor was employed to carry out the degradation experiments by means ofThe impacts on BPA degradation under the conditions of different ozone dosages, water background values

Keywords： BPA     scanning     reactor     process     O-HO    

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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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Interlayer-confined two-dimensional manganese oxide-carbon nanotube catalytic ozonation membrane for efficient water

Frontiers of Chemical Science and Engineering 2022, Volume 16, Issue 5,   Pages 731-744 doi: 10.1007/s11705-021-2110-6

Abstract: Catalytic ozonation technology has attracted copious attention in water purification owing to its favorableobtained via the intercalation of a carbon nanotube, was designed as a catalytic ozonation membrane reactorseparator to efficiently oxidize organic pollutants and enhance the control of membrane fouling during water

Keywords： catalytic membrane reactor     catalytic ozonation     nanoconfinement     two-dimensional manganese oxide    

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Intrinsic kinetics and external diffusion of catalytic steam gasification of fine coal char particles under pressurized

Xuantao Wu, Jie Wang

Frontiers of Chemical Science and Engineering 2019, Volume 13, Issue 2,   Pages 415-426 doi: 10.1007/s11705-018-1725-8

Abstract: Catalytic steam gasification of fine coal char particles was carried out using a self-made laboratory reactor

Keywords： coal char     catalytic steam gasification     pressure     kinetics     diffusion    

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Title Author Date Type Operation

Influence evaluation of loading conditions during pressurized thermal shock transients based on thermal-hydraulics

Jinya KATSUYAMA, Shumpei UNO, Tadashi WATANABE, Yinsheng LI

Journal Article

The Formation of the Improved Chinese Pressurized Water Reactor Technology—CPR1000

Pu Jilong

Journal Article

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

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

Journal Article

In-Vessel Melt Retention of Pressurized Water Reactors: Historical Review and Future Research Needs

Weimin Ma, Yidan Yuan, Bal Raj Sehgal

Journal Article

HPR1000: Advanced Pressurized Water Reactor with Active and Passive Safety

Ji Xing, Daiyong Song, Yuxiang Wu

Journal Article

CFD Simulation of thermal hydraulic characteristics in a typical upper plenum of RPV

Mingjun WANG, Lianfa WANG, Yingjie WANG, Wenxi TIAN, Jian DENG, Guanghui SU, Suizheng QIU

Journal Article

Non-pressurized Heating Reactor——a Realizable And Economical Clean Energy

Tian Jiafu

Journal Article

An old issue and a new challenge for nuclear reactor safety

F. D’AURIA

Journal Article

Discussions and practice of pressurized water injection for ultra low permeability oilfield

Zhang Hongliang

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

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

Lefu ZHANG, Fawen ZHU, Rui TANG

Journal Article

Degradation of endocrine disruptor bisphenol A in drinking water by ozone oxidation

XU Bin, GAO Naiyun, RUI Min, WANG Hong, WU Haihui

Journal Article

Overall Development Strategy of Materials Used for China’s New-Generation Nuclear Power Plants

Gan Yong, Zhao Xiangeng, Xu Kuangdi

Journal Article

Interlayer-confined two-dimensional manganese oxide-carbon nanotube catalytic ozonation membrane for efficient water

Journal Article

Intrinsic kinetics and external diffusion of catalytic steam gasification of fine coal char particles under pressurized

Xuantao Wu, Jie Wang

Journal Article