Results 41 to 50 of about 375 (173)

Brittle fracture resistance of reactor pressure vessel steels in the initial state [PDF]

open access: yesNuclear 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

Transmuting the Arid: Fission‐Powered Visions—Unlocking Ghana’s Aquatic Destiny Through Nuclear Desalination

open access: yesScience and Technology of Nuclear Installations, Volume 2026, Issue 1, 2026.
Water scarcity poses a mounting constraint on Ghana’s socioeconomic development, intensified by climate‐driven hydrological variability, rapid urbanization, and industrial expansion. This study presents a Ghana‐specific techno‐economic and policy‐integrated assessment of nuclear‐powered seawater desalination, moving beyond generic applications of ...
Felix Ameyaw   +3 more
wiley   +1 more source

Development of nodal diffusion code RAST-V for Vodo–Vodyanoi Energetichesky reactor analysis

open access: yesNuclear 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

Analysis With Different Containment Models for Containment Response of NHR200II Under Loss‐of‐Coolant Accident

open access: yesScience 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

open access: yesJournal 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

Experimental studies into the fluid dynamic performance of the coolant flow in the mixed core of the Temelin NPP VVER-1000 reactor

open access: yesNuclear 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

open access: yesInternational 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

A method for VVER fuel element cladding reliability prediction [PDF]

open access: yesЯдерна фізика та енергетика, 2014
Considering a VVER-1000 fuel assembly averaged fuel element (FE), based on the accepted FE cladding damage limit value, the FE cladding failure probability was determined, thus the possibility of this reliability pre-diction by means of controlling the ...
S. M. Pelykh   +2 more
doaj  

Assessing the Performance of Point and Two‐Point Kinetics Models in Simulating the Control Rod Drop Accident in VVER‐1000 Reactors

open access: yesInternational 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

The choice of the fuel assembly for VVER-1000 in a closed fuel cycle based on REMIX-technology

open access: yesEPJ Nuclear Sciences & Technologies, 2016
This paper shows basic features of different fuel assembly (FA) application for VVER-1000 in a closed fuel cycle based on REMIX-technology. This investigation shows how the change in the water–fuel ratio in the VVER FA affects on the fuel characteristics
Bobrov Evgenii   +4 more
doaj   +1 more source

Home - About - Disclaimer - Privacy