Results 181 to 190 of about 2,771 (221)

The AP1000 LBLOCA Analysis Using SCDAP/RELAP5

Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, 2014
In this study, a transient performance simulation model of AP1000 using SCDAP/RELAP5 4.0 is developed. The reactor coolant system (RCS) and passive core cooling system (PXS) are modeled respectively. Various kinds of hydrodynamic component including Volume, Junction, Separator, Accumulator, Branch, Pipe, Valve and Pump are adopted to simulate the fluid
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Large LOCA accident analysis for AP1000 under earthquake

Annals of Nuclear Energy, 2015
Abstract Seismic probabilistic safety assessment (PSA) is developed to give the insight of nuclear power plant risk under earthquake and the main contributors to the risk. However, component failure probability including the initial event frequency is the function of peak ground acceleration (PGA), and all the components especially the different ...
Yu Yu, Xuefeng Lv, Fenglei Niu
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Improvement of the Reactor Control System in AP1000

Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, 2017
AP1000 is a two-loop pressurized water reactor (PWR) developed by Westinghouse, which uses the forces of nature and simplicity of design to enhance plant safety and reduce construction costs. Compared to traditional reactor control strategies, the AP1000 adopts an advanced Mechanical Shim (MSHIM) core control strategy, which controls the reactivity and
Dai Chunhui, Wei Xinyu, Tao Mo, Wu Jun, Zhao Zhenxing, Liu Zhouyang, Liu Yong   +6 more
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Experimental investigation of upper plenum entrainment in AP1000

Progress in Nuclear Energy, 2015
Abstract 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, Y. Xiang, W.X. Tian, J.C. Liu, P. Zhang, S.Z. Qiu, G.H. Su   +6 more
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AP1000 core design with 50% MOX loading

Annals of Nuclear Energy, 2009
Abstract The European uility requirements (EUR) document states that the next generation European passive plant (EPP) reactor core design shall be optimized for UO 2 fuel assemblies, with provisions made to allow for up to 50% mixed-oxide (MOX) fuel assemblies. The use of MOX in the core design will have significant impacts on key physics parameters
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Reliability Assessment of Reactor AP1000 Passive ERVC System

Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, 2017
As the safety requirements level of nuclear power plant is gradually improving, more and more passive systems are used in the advanced type reactors. However, the reliability evaluation work for these passive systems is still in the primary stage. Therefore, in this paper the work is started based on the reliability evaluation process of passive system,
Cui Chengxin, Huang Ting, Chen Lian, Chen Ying, Zhang Lei   +4 more
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Margin Assessment of AP1000 Loss of Flow Transient

Volume 2: Thermal Hydraulics, 2006
The Reactor Coolant System (RCS) of the AP1000 plant consists of two circulating loops. Each loop contains two canned motor Reactor Coolant (RC) pumps that have a rotating inertia to provide RCS flow coastdown if power to the pumps is lost. Westinghouse analysis of the complete loss of flow (CLOF) accident in support of the AP1000 design certification ...
Edward L. Carlin, Peter A. Hilton, Yixing Sung   +2 more
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The Natural Circulation Characteristic Analysis of AP1000 IRWST

Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, 2014
The natural convection passive residual heat removal system is an essential system of AP1000 nuclear power plants, which works in the non-LOCA accident. It can discharge the waste heat in the reactor core timely, and prevent the reactor accident. The In-Containment Refueling Water Storage Tank (IRWST) is one of the most important equipments of passive ...
Ruojun Xue, Bin Xia, Wang Mingyuan
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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, 2017
In 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, Sun Hong-tao, Liu Jing-bo, Ma Ji-qiang, Liu Yuan   +4 more
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Analysis on hydrogen control system in AP1000 NPP

Annals of Nuclear Energy, 2018
Abstract 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, Zeyun Xun, Ke Ji, Xiaobo Lee, Shengfei Wang, Yu Yu, Long Chen   +6 more
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