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Experimental and Numerical Studies of AP1000 Shield Building considering Fluid-Structure Interaction
Science and Technology of Nuclear Installations, 2022 The gravity cooling water tank is a remarkable structural feature of third-generation pressurized water reactor nuclear power plant. To investigate the influence of fluid-structure interaction (FSI) on the seismic response of the structure, this study ...
Zhi Zhang +3 more
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A Comparison in Thermal-hydraulics Analysis of Pwr1000 Using Fixed and Temperature Function of Thermal Conductivity [PDF]
, 2016 A COMPARISON IN THERMAL-HYDRAULICS ANALYSIS OF PWR-1000 USING FIXEDAND TEMPERATURE FUNCTION OF THERMAL CONDUCTIVITY. A study to analyze theinfluence of the fuel-cladding's thermal conductivity on the sub-channel of pressurized waterreactor 1000 (PWR-1000)
Isnaini, M. D. (Muhammad) +1 more
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Ensembles of climate change models for risk assessment of nuclear power plants [PDF]
, 2017 Climate change affects technical Systems, Structures and Infrastructures (SSIs), changing the environmental context for which SSI were originally designed.
Al-Dahidi S +10 more
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Simulation of Spray Injection in the Pressurizer Using RELAP5 [PDF]
, 2017 A modeling research using Relap5 to assess the pressurizer of a pressurized water reactor(PWR) power plant has been performed. The heater and water injection systems in the pressurizer system of the PWRare of greatimportance for system pressure control ...
Dibyo, S. (S), Susyadi, S. (S)
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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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Nuclear Engineering and Technology, 2021 Nuclear emergency preparedness and response is an essential part to ensure the safety of nuclear power plant (NPP). Key support technologies of nuclear emergency decision-making usually consist of accident diagnosis, source term estimation, accident ...
Guohua Wu +4 more
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Primääripiirin jäähdytysjärjestelmän kuvaus osana Loviisan lopullista turvallisuusselostetta [PDF]
, 2015 Insinöörityön tarkoituksena oli tarkastella Loviisan ydinvoimalan turvallisuusselosteen lukua 5 Reaktorin jäähdytysjärjestelmä. Luvun rakenteeseen oli tarkoitus antaa kehitysehdotuksia ja alalukuun 5.1.
Hannola, Paula
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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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Energies, 2021 In the two-step method for nuclear reactor simulation, lattice physics calculations are performed to compute homogenized cross-sections for a variety of burnups and lattice configurations. A nodal code is then used to perform full-core analysis using the
Dean Price +4 more
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Development and Application of CAP1400 Numerical Reactor System
Yuanzineng kexue jishu, 2022 Numerical reactor technology describes a variety of physical phenomena in the core of a nuclear reactor through highprecision, highresolution, high confidence and high fidelity numerical simulation method, based on highperformance calculation and ...
CAO Liangzhi;DENG Li;YANG Bo;LIU Zhouyu;LIU Peng;TANG Chuntao;SHI Dunfu;CHEN Ronghua;TIAN Wenxi;PENG Lianghui;WAN Chenghui;ZHANG Minwan;BI Guangwen;FEI Jingran;XU Xiaobei;LI Fan
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