Results 41 to 50 of about 688 (173)

Synergies in VVER reactor long-term operation and aging: A comprehensive review of CAMIVVER, DELISA-LTO, and EVEREST projects

EPJ Nuclear Sciences & Technologies
This paper reviews the synergies between three Euratom projects–CAMIVVER, DELISA-LTO, and EVEREST–focusing on the long-term operation (LTO) and safety assessment of VVER reactors.
Hursin Mathieu, Perin Yann, Verrier Denis, Slugen Vladimir, Veternikova Jana Simeg   +4 more
doaj   +1 more source

CATHARE Assessment of PACTEL LOCA Experiments with Accident Management

Science and Technology of Nuclear Installations, 2010
This paper summarizes the analysis results of three PACTEL experiments, carried out with the advanced thermal-hydraulic system computer CATHARE 2 code as a part of the second work package WP2 (analytical work) of the EC project “Improved Accident ...
Luben Sabotinov, Heikki Purhonen, Vesa Riikonen   +2 more
doaj   +1 more source

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

Science 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, Etornam Akaho, Seth Debrah, Doddy Kastanya   +3 more
wiley   +1 more source

VVER Knowledge Preservation and Transfer within the Frame of CORONA Project Activities

EPJ Web of Conferences, 2016
The CORONA project is funded by the European Commission under the FP7 programme with overall objective to establish a Regional Centre of Competence for VVER Technology and Nuclear Applications.
Mitev Mladen, Corniani Enrico, Manolova Maria, Pironkov Lybomir, Tsvetkov and Iskren   +4 more
doaj   +1 more source

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

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, Yifan Meng, Zixuan Wang, Mohammad Rezwan Habib   +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, Heather Graven, Giulia Zazzeri, Benjamin Hmiel, Vasilii V. Petrenko, Andrew M. Smith, Sylvia E. Michel, Shinji Morimoto   +7 more
wiley   +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, Jing Shang, Longwei Mei, Jianfei Tong, Yashwant Sawle   +4 more
wiley   +1 more source

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

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, Rajashik Paul   +1 more
wiley   +1 more source

Pressurized Water Reactor Transient Detection With Artificial Intelligence to Support Reactor Operators

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, Senem Şentürk Lüle, Han Zhang   +2 more
wiley   +1 more source

Development of Emergency Planning Zones for Ghana’s Proposed Nuclear Plant Based on Radioactivity Releases From Hypothetical Accident Scenarios

Science and Technology of Nuclear Installations, Volume 2025, Issue 1, 2025.
Emergency planning zones (EPZs) for Ghana’s potential reactor site have been determined based on an assessment of atmospheric dispersion and dose calculations for multiple accident scenarios involving a VVER‐1200 reactor. The analysis was performed using the Radiological Assessment System for Consequence Analysis (RASCAL) 4.3.4 code to calculate doses ...
Alberta Blay, Sylvester Attakorah-Birikorang, Esi Awuah, Manish Sharma   +3 more
wiley   +1 more source