Results 31 to 40 of about 1,699,034 (145)
Nuclear Engineering and Technology, 2021 The thermal hydraulic performances of Steam Generator (SG) under both steady and transient operation conditions are of great importance for the safety and economy in nuclear power plants.
Xiaohan Zhao +6 more
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Energies, 2022 Best estimate system thermal-hydraulic codes in the nuclear engineering community, e.g., TRACE, RELAP3D, CATHARE-3, etc., were extended with 3D coarse-mesh components to better describe the 3D Thermal-Hydraulic (TH) phenomena taking place within the ...
Kanglong Zhang +1 more
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Sensitivity Evaluation of AP1000 Nuclear Power Plant Best Estimation Model
Science and Technology of Nuclear Installations, 2017 The best estimation process of AP1000 Nuclear Power Plant (NPP) requires proper selections of parameters and models so as to obtain the most accurate results compared with the actual design parameters.
Hao Shi, Qi Cai, Yuqing Chen
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Dynamic Analysis of AP1000 Shield Building Considering Fluid and Structure Interaction Effects
Nuclear Engineering and Technology, 2016 The shield building of AP1000 was designed to protect the steel containment vessel of the nuclear reactor. Therefore, the safety and integrity must be ensured during the plant life in any conditions such as an earthquake.
Qiang Xu +4 more
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Thermal Science, 2020 The heat transfer performance of the spent fuel transport cask is inseparably related to the safety of the whole reprocessing system. In this study, we carried out the thermal analysis on the NAC-STC transport cask for AP1000 spent fuel assembly to evaluate the thermal performance of transport cask by the finite element method software ANSYS.
Shujian Tian +5 more
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Evaluation of Passive Safety Injection System Performance Under Large Break LOCA for Qinshan PWR
Frontiers in Energy Research, 2021 In this work, a brand new passive safety injection system has been designed for the ocean-based Qinshan Phase I nuclear power plant to update and replace the traditional active ones. The passive safety injection system is made up of high pressure, medium
Xuesong Wang +3 more
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Introduction to Nuclear Reactor Experiments [PDF]
, 2023 This open access book is a pedagogical text on nuclear reactor experiments, covering almost all the experiments that can be carried out at the University Training Reactor, Kindai University (UTR-KINKI) with respect to reactor physics and radiation ...
Endo, Tomohiro +3 more
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The General Design and Technology Innovations of CAP1400
Engineering, 2016 The pressurized water reactor CAP1400 is one of the sixteen National Science and Technology Major Projects. Developed from China's nuclear R&D system and manufacturing capability, as well as AP1000 technology introduction and assimilation, CAP1400 is an ...
Mingguang Zheng +5 more
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Nuclear Engineering and Technology, 2019 The AP1000 reactor coolant pump is a vertical shielded-mixed flow pump, is the most important coolant power supply and energy exchange equipment in nuclear reactor primary circuit system, whose steady-state and transient performance affect the safety of ...
Xiuli Wang +5 more
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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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