Results 41 to 50 of about 72 (58)
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Transient analysis of AP1000 NPP under the similar Fukushima accident conditions

Annals of Nuclear Energy, 2017
Abstract Stress tests are conducted on AP1000 NPP to investigate the effectiveness of Passive Core Cooling System (PXS) in mitigating the similar Fukushima accident conditions, using thermal hydraulic analysis code RELAP. Key transient parameters, including the Reactor Coolant System (RCS) pressure, core coolant temperature and passive safety system
Ting Wang, Xi Huang, Ren Liang
exaly   +2 more sources

Effect on hydrogen risk of total amount of inert gas during post-inerting in AP1000 NPP

Annals of Nuclear Energy, 2020
Abstract To study the hydrogen risk at severe accident of LB-LOCA of cold leg in 1# SG compartment with gravity injection failure and hydrogen igniters without power in AP1000 NPP, we investigate the effect of total amount of inert gas on reducing hydrogen risk during AP1000 post-inerting. The total amount of inert gas is 42 tons, 56 tons and 70 tons
Xuefeng Lyu
exaly   +2 more sources

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.
Shengfei Wang, Xuefeng Lyu
exaly   +2 more sources

Vibration Reduction Mechanism and NPPs Seismic Safety of TMD Shield Building for AP1000 NPPs

Volume 8: Seismic Engineering, 2018
Without additional mass, the tuned mass damping (TMD) shield building for AP1000 Nuclear Power Plants (NPPs) was achieved easily by changing the stiffness and damper between parts of shield building. Meanwhile, the new TMD structure combined the structural features of the shield building with TMD technology.
Gang Zheng   +3 more
openaire   +1 more source

Integrated Functional Modeling Method for Configuring NPP Plant DiD Risk Monitor and its Application for AP1000

Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, 2014
A new risk monitor system has been under developing, in order not only to prevent severe accident in daily operation but also even to serve as to mitigate the radiological hazard just after severe accident happens and long term management of post-severe accident consequences.
Hidekazu Yoshikawa   +3 more
openaire   +1 more source

Utilizing the Purified Orbit Curve Technical in AP1000 NPP Turbine Diagnosis (Monitoring) Systems

Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, 2013
To improve the diagnosis accuracy and self-adaptability of steam turbine diagnosis systems in AP1000 NPP, this article attempts to apply a new method which unifies digital filter and stimulant filter into the filter processing of turbine Shaft vibration signal in Nuclear Power Plant. According to the process of power plant field data guideline, 4-level
openaire   +1 more source

Validation of NECP-Bamboo with BEAVRS and AP1000 measurements

Nuclear Engineering and Design, 2021
Hongchun Wu
exaly  

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

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

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