Results 141 to 150 of about 280 (176)
Some of the next articles are maybe not open access.

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, 2016
Passive 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
openaire   +1 more source

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
openaire   +1 more source

Emergency Operating Procedures (EOPs) for the AP1000 Simulator

Volume 5: Safety and Security; Low Level Waste Management, Decontamination and Decommissioning; Nuclear Industry Forum, 2006
The 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
openaire   +1 more source

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   +2 more
openaire   +1 more source

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
openaire   +1 more source

HPF compiler for the AP1000

Proceedings of the 9th international conference on Supercomputing - ICS '95, 1995
Tatsuya Shindo   +4 more
openaire   +2 more sources

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, 2009
As 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 ...
openaire   +1 more source

Study on the Localization of Instrumentation Installation Materials for AP1000

2017
This paper analyzed the standards of instrumentation installation components for the nuclear island of AP1000 NPP, made a comparison with Chinese standards, studied the localization of the instrumentation tube and fittings, and proposed the material substitution principles during construction.
Shuen Lu, Chengli Qin, Haibo Wu
openaire   +1 more source

Safety assessment of AP1000: Common transients, analysis codes and research gaps

Nuclear Engineering and Design, 2021
Muritala Amidu   +2 more
exaly  

Gray Rod Control Assembly for AP1000

Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan, 2012
Yoshioka, Kenichi   +5 more
  +4 more sources

Home - About - Disclaimer - Privacy