Results 41 to 50 of about 399 (171)
Nuclear Engineering and Technology, 2023 The specific configuration of the safety systems in VVER-1000/V320 reactors allows a comprehensive study of the Loss of Coolant Accident (LOCA). In the present paper, a verification of the success criteria of the event trees headers for the medium and ...
Elena Redondo-Valero +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
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
Nuclear Energy and Technology, 2015 The paper presents the results of studies into the interassembly coolant interaction in the Temelin nuclear power plant (NPP) VVER-1000 reactor core.
S.M. Dmitriev +5 more
doaj +1 more source
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
Brittle fracture resistance of reactor pressure vessel steels in the initial state [PDF]
Nuclear Energy and Technology, 2018 The authors investigate the influence of chemical and structural inhomogeneity on the brittle fracture resistance (BFR) of VVER vessel materials in the initial state (without irradiation).
Nikolay P. Anosov +5 more
doaj +3 more sources
Development of nodal diffusion code RAST-V for Vodo–Vodyanoi Energetichesky reactor analysis
Nuclear Engineering and Technology, 2022 This paper presents the development of a nodal diffusion code, RAST-V, and its verification and validation for VVER (vodo–vodyanoi energetichesky reactor) analysis.
Jaerim Jang +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
OPTIMIZATION OF POWER LOAD FOLLOWING MODES FOR VVER-1000
POWER ENGINEERING: economics, technique, ecologyThe need to involve nuclear power plants in daily power regulation is driven by the gradual increase in the share of renewable energy sources in the Unified Energy System (UES) of Ukraine. Additionally, the conditions for implementing measures to address climate change and deteriorating operating conditions of the UES in the face of economic changes
Svyatoslav Kobrynchuk, Maksym Ieremenko
openaire +2 more sources