Results 131 to 140 of about 280 (176)
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AP1000 Fuel Design and Core Operations
Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues, 2008This paper discusses the key features of the Fuel design and Core Operations of the AP1000 reactor. Core Design and thermal parameters are compared to those of existing Westinghouse reactors. Details of the Fuel Assembly design are provided, along with relevant operating experience.
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Toward lattice QCD simulation on AP1000
Nuclear Physics B - Proceedings Supplements, 1992Abstract AP1000 is Fujitsu Laboratory's experimental parallel computer consisting of up to 1024 microcomputers called cells. It is found that each AP1000 cell can sustain two to three megaflops computational speed for full QCD lattice numerical simulations in IEEE 64-bit floating point ...
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Analysis of safety margin of in-vessel retention for AP1000
Nuclear Engineering and Design, 2010In-vessel retention (IVR) of core melt is a key severe accident management strategy adopted by most operating nuclear power plants and advanced light water reactors (ALWRs), AP600, AP1000, etc. External reactor vessel cooling (ERVC) is a novel severe accident management for IVR analysis.
Y.P. Zhang, S.Z. Qiu, G.H. Su, W.X. Tian
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Experimental investigation of upper plenum entrainment in AP1000
Progress in Nuclear Energy, 2015Abstract Upper plenum liquid entrainment can reduce the coolant inventory in the reactor pressure vessel and poses great threats to core uncovering and melting in the accident conditions. To make up for the deficiency of upper plenum entrainment database, the Automatic Depressurization and Entrainment TEst Loop (ADETEL) was constructed and upper ...
D.C. Sun +6 more
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Study of AP1000 Protection System Based on FirmSys
Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, 2017In order to design AP1000 protection system based on the FirmSys platform of CTEC, the AP1000 protection system based on CommonQ platform is analyzed and researched. Through the comparison of the FirmSys platform and the CommonQ platform, it is found that the number of cabinets should be increased largely if the protection system design based on the ...
Zheng Wei-zhi +4 more
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The SCDAP/RELAP5 3.2 model of AP1000 on SBLOCA
Progress in Nuclear Energy, 2012Abstract One of innovation design of both the AP600 and AP1000 from conventional Westinghouse PWRs is that they includes passive safety features to prevent or minimize core uncovery during small break loss of coolant accidents (SBLOCAs). This paper uses the best estimate code SCDAP/RELAP5 3.2 to build the numerical model of AP1000.
Heng Xie, Shuangji He
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AP1000 Plant Availability Analysis in Accordance With the EUR
Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition, 2009As part of the European Passive Pressurized Water reactor (EPP) Program, AP1000 plant availability analyses and studies were performed to show compliance with the European Utility Requirements (EUR) goal of an overall plant availability greater than 90%.
Richard G. Anderson +5 more
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AP1000® SBLOCA simulations with TRACE code
Annals of Nuclear Energy, 2015Abstract The AP1000 ® is an advanced pressurized water reactor (PWR) design developed by Westinghouse which implements passive safety systems to provide core cooling in case of accident. The performing of such systems must be evaluated through the performance of experiments and simulations with a variety of thermal–hydraulic codes.
J. Montero-Mayorga +2 more
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The First AP1000 Fuel Fabrication Line in China
2017The purpose of this paper is to present a description about the first AP1000 fuel fabrication line in Baotou, China. Owned by China Baotou Nuclear Fuel Corporation (CBNF), the facility construction was started in March, 2012. A capacity of 400 TU/year of fabrication from IFBA pellet fabrication through final fuel assembly, as well as manufacturing of ...
Shuangqing Shi, Zhigang Wang
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Analysis on hydrogen control system in AP1000 NPP
Annals of Nuclear Energy, 2018Abstract The three-dimensional computational fluid dynamics code GASFLOW is employed to analyze hydrogen behavior and risk at the accident of a small break of cold leg in 1# steam generation compartment with ADS4 unavailable in AP1000 nuclear power plant.
Xuefeng Lyu +6 more
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