Results 51 to 60 of about 1,033,988 (155)
Worst‐Case Accident Analysis of Accident Tolerant Fuel in NuScale Using RELAP5/MOD3‐Based Code
International Journal of Energy Research, Volume 2024, Issue 1, 2024.Research in nuclear engineering focusses on improving the safety of light water reactors (LWRs), driven by accidents like Fukushima in 2011. The severity of this accident was a result of active cooling system failures and cladding material oxidation resulting in hydrogen explosions.
Willem Zuidersma +3 more
wiley +1 more source
Science and Technology of Nuclear Installations, Volume 2016, Issue 1, 2016., 2016 Small modular reactor (SMR) has drawn wide attention in the past decades, and Lead cooled fast reactor (LFR) is one of the most promising advanced reactors which are able to meet the safety economic goals of Gen‐IV nuclear energy systems. A small modular natural circulation lead cooled fast reactor‐100 MWth (SNRLFR‐100) is being developed by University
Pengcheng Zhao +5 more
wiley +1 more source
Journal of Nuclear EngineeringThe molten salt reactor (MSR) is a prominent Generation IV nuclear reactor concept that offers substantial advantages over conventional solid-fueled systems, including enhanced fuel utilization, inherent passive safety features, and significant ...
Hossam H. Abdellatif +3 more
doaj +1 more source
Application of the RELAP5-3D code in support of the NPP units safety analysis in Ukraine [PDF]
Ядерна фізика та енергетика, 2006 Major part of calculations for transient and accident sequences for Ukraine NPP units has been performed with computational codes based on point neutron kinetics and one dimensional thermohydraulics. Such an approach does not allow modelling the mixing
A. M. Shkarupa, I. N. Kadenko
doaj
Integrated Software Environment for Pressurized Thermal Shock Analysis
Science and Technology of Nuclear Installations, 2011 The present paper describes the main features and an application to a real Nuclear Power Plant (NPP) of an Integrated Software Environment (in the following referred to as “platform”) developed at University of Pisa (UNIPI) to perform Pressurized Thermal
Dino Araneo +6 more
doaj +1 more source
RELAP5-3D Resolution of Known Restart/Backup Issues [PDF]
, 2014 The state-of-the-art nuclear reactor system safety analysis computer program developed at the Idaho National Laboratory (INL), RELAP5-3D, continues to adapt to changes in computer hardware and software and to develop to meet the ever-expanding needs of the nuclear industry.
George L. Mesina, Nolan A. Anderson
openaire +1 more source
Journal of Nuclear EngineeringRecent advances in high-fidelity modeling, numerical computing, and data science have spurred interest in model-data integration for nuclear reactor applications.
Lanxin Gong +2 more
doaj +1 more source
, 2020 " 3DHOP (3D Heritage Online Presenter) is an open-source software package for the creation of interactive Web presentations of high-resolution 3D models, oriented to the Cultural Heritage field....
Consortium 3D SHS Team
core
The Influence of the Packing Factor on the Fuel Temperature Hot Spots in a Particle-Bed GCFR
Science and Technology of Nuclear Installations, 2009 In the recent past the so-called GCFR has been again a subject of study by the international scientific community. This type of reactors, although still in a preliminary stage of development, is a very interesting perspective because combines the ...
G. Lomonaco, W. Grassi, N. Cerullo
doaj +1 more source
Conservatoire des Données 3D SHS
, 2020 ” Le Conservatoire National des Données 3D SHS est un environnement de sauvegarde sécurisé pour les données 3D, soutenu par Huma-Num.. …
Consortium 3D SHS Team
core