Results 141 to 150 of about 272 (179)
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Use of PRA in the Design of the Westinghouse AP1000 Plant
Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 2009Probabilistic Risk Assessment (PRA) has been an integral part of the Westinghouse AP1000, and the former AP600, development programs from its inception. The design of the AP1000 plant is based on engineering solutions to reduce or eliminate many of the dominant risk contributors found in the existing generation of Pressurized Water Reactors (PWRs ...
Robert J. Lutz +3 more
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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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Advanced First Core Design for the Westinghouse AP1000
Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control, 2009As the nuclear renaissance is now upon us and new plants are either under construction or being ordered, a considerable amount of attention has also turned to the design of the first fuel cycle. Requirements for core designs originate in the Utilities Requirements Document (URD) for the United States and the European Utilities Requirements (EUR) for ...
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Reliability of PCCS in AP1000 Based on Accident Development
Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, 2016Passive containment cooling system (PCCS) is an important safety-related system in AP1000 nuclear power plant, by which heat produced in reactor is transferred to the heat sink – atmosphere – based on natural circulation, independent of human response or the operation of outside equipments, so the reactor capacity of resisting external hazards ...
Yu Yu, Shengfei Wang, Fenglei Niu
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Emergency Operating Procedures (EOPs) for the AP1000 Simulator
Volume 5: Safety and Security; Low Level Waste Management, Decontamination and Decommissioning; Nuclear Industry Forum, 2006The AP1000 is two-loop 1100 MWe advanced pressurized water reactor (PWR) that uses passive safety features to enhance plant safety and to provide significant and measurable improvements in plant simplification, reliability, investment protection and plant costs.
Yuichi Hayashi +2 more
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The AP1000 LBLOCA Analysis Using SCDAP/RELAP5
Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, 2014In 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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Post-Fukushima Assessment of the AP1000® Plant
Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, 2014The AP1000 plant is an 1100-MWe class pressurized water reactor with passive safety features and extensive plant simplifications that enhance construction, operation, maintenance, and safety with reduced plant costs. The AP1000 passive nuclear power plant is uniquely equipped to withstand an extended station blackout scenario such as the events ...
Terry L. Schulz +5 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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Proceedings of the 9th international conference on Supercomputing - ICS '95, 1995
Tatsuya Shindo +4 more
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Tatsuya Shindo +4 more
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Gray Rod Control Assembly for AP1000
Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan, 2012Tahara, Yoshihisa +2 more
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