Results 41 to 50 of about 302 (158)
Study of the VVER1000 reactor core fuel assemblies reaction to mass flux changes, caused by lose of coolant accident, by means of the sound effect [PDF]
مجله علوم و فنون هستهای, 2019 The article aims in the studying of thermal-hydraulic simulation of the VVER-1000 reactor core fuel assemblies’ reaction to the mass flux changes which are caused by the lose of coolant accident and its sudden pressure drop.
S Heidari +3 more
doaj +1 more source
Science and Technology of Nuclear Installations, Volume 2026, Issue 1, 2026.In the design of nuclear power plant systems, the thermal–hydraulic response in the containment during a loss‐of‐coolant accident (LOCA) plays a crucial role. In this study, the advanced small modular reactor NHR200‐II is selected as the research object.
Yan Wang +3 more
wiley +1 more source
In-service change in the flexural rigidity of the VVER-1000 fuel assemblies
Nuclear Energy and Technology, 2016 In-service dimensional stability of the VVER-1000 reactor fuel assemblies (FA) depends to a great extent on their flexural rigidity. A decrease in the flexural rigidity in the process of the FA operation in the reactor may lead to such FA bowing as will ...
S.V. Pavlov
doaj +1 more source
Global Fossil Methane Emissions Constrained by Multi‐Isotopic Atmospheric Methane Histories
Journal of Geophysical Research: Atmospheres, Volume 130, Issue 5, 16 March 2025.Abstract The global CH4 budget of sources and sinks is highly uncertain, particularly the emissions from specific sources such as fossil fuels (FF) or agriculture. Here, we estimate plausible global CH4 source and sink scenarios using historical observations and simulations of atmospheric CH4 mole fraction and its stable isotopic (δ13C‐CH4, δD‐CH4) and
Ryo Fujita +7 more
wiley +1 more source
Investigation of DPA in the reactor pressure vessel of VVER-1000/V320
Nuclear Science and Technology, 2017 The most important ageing effect on the reactor pressure vessel (RPV) is radiation embrittlement, which is mainly caused by fast neutrons during operation lifetime of nuclear reactors. The aim of this study was to investigate the DPA (displacement per atom) rate, an important parameter describing radiation damage to the RPV, and identify the position ...
Huu Tiep Nguyen +2 more
openaire +2 more sources
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
International Journal of Energy Research, Volume 2025, Issue 1, 2025.Reactivity‐initiated accidents (RIAs), such as the control rod drop accident (CRDA), are classified as design‐basis accidents (DBAs) in the final safety analysis report (FSAR) of a nuclear power plant (NPP), and investigating these events is crucial.
Seyed Mohammad Hossein Mousakazemi +1 more
wiley +1 more source
Estimation of Control Rod Worth in a VVER-1000 Reactor using DRAGON4 and DONJON4
Nukleonika, 2014 One of the main issues in safety and control systems design of power and research reactors is to prevent accidents or reduce the imposed hazard. Control rod worth plays an important role in safety and control of reactors.
Saadatian-derakhshandeh Farahnaz +2 more
doaj +1 more source
Science and Technology of Nuclear Installations, Volume 2025, Issue 1, 2025.Nuclear reactors are subject to strict safety standards due to the critical nature of operational safety. Detecting transients as fast and accurately as possible is essential to reactor safety especially to reduce the human error of operators. In order to enhance this process, artificial intelligence (AI) offers strong opportunities.
Ceyhun Yavuz +2 more
wiley +1 more source
Improved Heat Transfer Capabilities of Nanofluids—An Assessment Through CFD Analysis
Chemical Engineering &Technology, Volume 47, Issue 11, November 2024.Conventional fluids used in fission‐based water‐cooled nuclear reactors have lower heat transfer coefficients and thermal conductivity, prompting researchers to explore high‐performance fluids to enhance heat transfer and prevent core meltdown during accidents. It is crucial to investigate fluids that can improve thermal hydraulic characteristics, such
Rehan Zubair Khalid +4 more
wiley +1 more source