Results 41 to 50 of about 1,365 (205)
Passive Hydrogen Recombination during a Beyond Design Basis Accident in a Fusion DEMO Plant
Energies, 2023 One of the most important environmental and safety concerns in nuclear fusion plants is the confinement of radioactive substances into the reactor buildings during both normal operations and accidental conditions.
Matteo D’Onorio +4 more
doaj +1 more source
MELCOR steady state calculation of the generic PWR of 40MWth
Brazilian Journal of Radiation Sciences, 2021 After the two most significant nuclear accidents in history – the Chernobyl Reactor Four explosion in Ukraine (1986) and the Fukushima Daiichi accident in Japan (2011) –, the Final Safety Analysis Report (FSAR) included a new chapter (19) dedicated to ...
Maritza Rodríguez Gual +2 more
doaj +1 more source
Analyses of hydrogen risk in containment filtered venting system using MELCOR
Nuclear Engineering and Technology, 2022 Hydrogen risk in the containment filtered venting system (CFVS) vessel was analyzed, considering operation pressure and modes with the effect of PAR and accident scenarios. The CFVS is to depressurize the containment by venting the containment atmosphere
Gi Hyeon Choi +2 more
doaj +1 more source
, 2022 The goal of this activity is to apply and test Uncertainty Quantification (UQ) methodologies with MELCOR 2.2 against the PHEBUS FPT1 test using three different methodologies and the same MELCOR input deck: RAVEN (Sapienza) DAKOTA coupling with Python ...
S. Paci +6 more
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MELCOR model for an experimental 17x17 spent fuel PWR assembly. [PDF]
, 2010 A MELCOR model has been developed to simulate a pressurized water reactor (PWR) 17 x 17 assembly in a spent fuel pool rack cell undergoing severe accident conditions.
Jeffrey Cardoni, Cardoni, Jeffrey
core +1 more source
Effect of Molten Corium Behavior Uncertainty on the Severe Accident Progress
Science and Technology of Nuclear Installations, 2018 Uncertainty of a severe accident code output needs to be handled reliably considering its use in safety regulation of nuclear industry. In particular, severe accident codes are utilized for probabilistic safety assessment (PSA), where the uncertainty of ...
Wonjun Choi +4 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
MELCOR 1.8.2 assessment: Surry PWR TMLB` (with a DCH study) [PDF]
, 1994 MELCOR is a fully integrated, engineering-level computer code, being developed at Sandia National Laboratories for the USNRC. This code models the entire spectrum of severe accident phenomena in a unified framework for both BWRs and PWRs.
Smith, R. C. +4 more
core +1 more source
Meteorological Applications, Volume 32, Issue 5, September/October 2025.A test bench has been developed allowing for the simulation of air flow in a 20 L cylindrical stainless‐steel chamber under conditions of the stratosphere and the troposphere: pressure from about 500 to 30 hPa, air temperature from 20°C to −50°C, and air flow velocity of about 5 m/s.
Michel Chartier +7 more
wiley +1 more source
An attempt to introduce a resuspension model in MELCOR 1.8.6 for fusion applications [PDF]
, 2017 During normal plasma operation the erosion of the ”plasma facing components” occurs and the dusts formed tends to deposit onto the divertor surface. In case of an In-vessel LOCA, these dusts may resuspend and transported to the VV Pressure Suppression ...
GONFIOTTI, BRUNO, PACI, SANDRO
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