BEPU analysis of a passive decay heat removal system with RELAP5/MOD3. 3 and RELAP5-3D
Passive safety systems are currently implemented or under consideration in several
advanced nuclear plants. In the Best-Estimate Plus Uncertainty (BEPU) approach it is …
advanced nuclear plants. In the Best-Estimate Plus Uncertainty (BEPU) approach it is …
SMRs—overview, international developments, safety features and the GRS simulation chain
A Schaffrath, A Wielenberg, R Kilger, A Seubert - Frontiers in Energy, 2021 - Springer
The Gesellschaft für Anlagen-und Reaktorsicherheit (GRS) gGmbH as the main technical
support organization for the German Federal Government in nuclear safety has been …
support organization for the German Federal Government in nuclear safety has been …
Ingress of Coolant Event simulation with TRACE code with accuracy evaluation and coupled DAKOTA Uncertainty Analysis
Abstract Among the Postulated Initiating Events in nuclear fusion plants, the Ingress of
Coolant Event (ICE) in the Plasma Chamber is one of the main safety issues. In the present …
Coolant Event (ICE) in the Plasma Chamber is one of the main safety issues. In the present …
[HTML][HTML] MELCOR–DAKOTA coupling for uncertainty analyses in the SNAP environment/architecture
Uncertainty estimation to assess figures of merit characterizing evolution of a severe
accident transient is a topic of current investigation in development of best-estimate plus …
accident transient is a topic of current investigation in development of best-estimate plus …
[HTML][HTML] Scaling-up assessment of natural circulation phenomena in integral Small Modular Reactor by TRACE code
Abstract Small Modular Reactors (SMRs) adopting passive mitigation strategies are
currently the most promising technology for the near term deployment of nuclear power …
currently the most promising technology for the near term deployment of nuclear power …
[HTML][HTML] Application of REPAS to analyze the sump clogging issue following a LOCA and its impact on the reliability of the ECCS long-term core cooling function
Sump clogging has been identified as a relevant issue after an accident occurred in the
Barsebäck-2 nuclear power plant in Sweden (1992). Following a steam line Loss of Coolant …
Barsebäck-2 nuclear power plant in Sweden (1992). Following a steam line Loss of Coolant …
Analysis of the OSU-MASLWR 001 and 002 Tests by Using the TRACE Code
F Mascari, F De Rosa, BG Woods, K Welter, G Vella… - 2016 - arpi.unipi.it
Abstract The Oregon State University (OSU) has constructed, under a US Department of
Energy grant, a scaled integral test facility to examine natural circulation phenomena …
Energy grant, a scaled integral test facility to examine natural circulation phenomena …
Small modular reactors and insights on passive mitigation strategy modeling
In the last decades, taking into account the operational experience of fission nuclear
reactors, the nuclear international technical community started the development of advanced …
reactors, the nuclear international technical community started the development of advanced …
[HTML][HTML] Reprint of “The role of nuclear thermal-hydraulics in the licensing of Atucha-II: The LBLOCA”
O Mazzantini, G Galassi, F D'Auria - Nuclear Engineering and Design, 2019 - Elsevier
The paper deals with the safety evaluation and the embedded licensing process of the
Atucha-II 800 Mwe Pressurized Heavy Water Reactor (PHWR) in Argentina. Atucha-II was …
Atucha-II 800 Mwe Pressurized Heavy Water Reactor (PHWR) in Argentina. Atucha-II was …
ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR
P Maccari, F Mascari, S Ederli, P Meloni… - Annals of Nuclear …, 2021 - Elsevier
Advanced small LWRs, are considered as one of the key design options for the development
of a safer nuclear technology considering their inherent safety due to the adoption of passive …
of a safer nuclear technology considering their inherent safety due to the adoption of passive …