Results 31 to 40 of about 280 (176)
Performance Analysis of AP1000 Passive Systems during Direct Vessel Injection (DVI) Line Break
Atom Indonesia, 2016 Generation II Nuclear Power Plants (NPPs) have a design weakness as shown by the Fukushima accident. Therefore, Generation III+ NPPs are developed with focus on improvements of fuel technology and thermal efficiency, standardized design, and the use of ...
A.S. Ekariansyah, S. Widodo
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Casting process design and practice for coolant pump impeller in AP1000 nuclear power station [PDF]
China Foundry, 2020 The coolant pump impeller casting is the only rotating component in the nuclear island of an AP1000 nuclear power station, and is required to have a 60-year service time, which requires advanced materials and processing technologies to guarantee. In this
Ping Zhao, Zhong-li Liu, Gui-quan Wang
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Wall-thickness reduction of AP1000 primary coolant pipes subjected to cold roll-forming
工程科学学报, 2016 A modified Johnson-Cook model was proposed based on the true stress-strain data of 316LN stainless steel and it was successfully used to describe the deformation characteristic of the steel at room temperature and low strain rate.
WANG Peng +3 more
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Nuclear Engineering and Technology, 2019 Seismic safety is considered to be one of the key design objectives of AP1000 nuclear power plant (NPP) in strong earthquakes. Dynamic behavior, damage development and aggravation effect are studied in this study for the three main components of AP1000 ...
Wanruo Chen +3 more
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Radiation shielding analysis and criticality safety calculation for spent fuel transportation cask [PDF]
EPJ Web of ConferencesChina anticipates a shortage in storage capacity for spent fuels at reactor sites for the AP1000 NPPs within the next 10 to 20 years. We proposed a conceptual design for a transportation cask capable of loading 21 spent fuel assemblies in AP1000 reactors
Chen Xiaosong +3 more
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Trudy Odesskogo Politehničeskogo UniversitetaAP1000 power units have great advantages over VVER-1000 power units which are popular in Ukraine. They are equipped with passive safety systems that significantly reduce the risks of man-made accidents, even under conditions of extreme external ...
Марк Петрович Галацан +1 more
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Science and Technology of Nuclear Installations, 2015 Huge water storage tank on the top of many buildings may affect the safety of the structure caused by fluid-structure interaction (FSI) under the earthquake.
Daogang Lu, Yu Liu, Xiaojia Zeng
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The detection and diagnosis model for small scale MSLB accident
Nuclear Engineering and Technology, 2021 The main steam line break accident is an essential initiating event of the pressurized water reactor. In present work, the fuzzy set theory and the signal-based fault detection method has been used to detect the occurrence and diagnosis of the location ...
Meng Wang, Wenzhen Chen
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Development and Verification of a Spatial Dynamics Code RESTA‐3D for Light Water Reactors
International Journal of Energy Research, Volume 2025, Issue 1, 2025.A neutronics/thermal‐hydraulics (TH) coupled spatial dynamics code, reactor system transient analysis‐three dimensional (RESTA‐3D), has been developed for both static and transient analysis of large advanced light water reactors (LWRs), with a focus on control rod (CR) ejection accidents.
Yong Cui +4 more
wiley +1 more source
East European Journal of PhysicsAccording to the strategic importance of Ukraine’s nuclear energy sector modernization, the results of investigation in the development and analysis of the cycle configuration of a steam turbine unit (STU) intended for operation with the AP1000 nuclear ...
Andrii V. Rusanov +5 more
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