Results 1 to 10 of about 1,365 (205)
Developing an Australian Melanoma Clinical Outcomes Registry (MelCOR): a protocol paper [PDF]
BMJ Open, 2022 Introduction Australia has the highest incidence of melanoma in the world with variable care provided by a diverse range of clinicians. Clinical quality registries aim to identify these variations in care and provide anonymised, benchmarked feedback to ...
John Zalcberg +14 more
doaj +5 more sources
MELGYM: A dynamic control interface for MELCOR simulations [PDF]
SoftwareXMELCOR is a computer code for the simulation and safety analysis of nuclear facilities, comprising several modules for the calculation of thermal–hydraulic phenomena and aerosol physics.
Antonio Manjavacas +4 more
doaj +4 more sources
Nuclear Engineering and Technology, 2022 In the present study, the cavity module of the MELCOR code is used for the simulation of molten corium concrete interaction (MCCI) during the late phase of postulated large break loss of coolant (LB-LOCA) accident in the APR1400 reactor design. Using the
Muritala Amidu, Yacine Addad
exaly +3 more sources
MODELING LOFW IN A PWR USING MELCOR
Brazilian Journal of Radiation Sciences, 2021 The Probabilistic Safety Assessment (PSA) is part of a Nuclear Power Plant (NPP) licensing process. It considers the elaboration and updating of probabilistic models that estimate the risk associated to the operation, allowing the risk monitoring from ...
Maritza Rodríguez Gual +3 more
doaj +3 more sources
Stand-alone containment analysis of Phébus FPT tests with ASTEC and MELCOR codes: the FPT-2 test [PDF]
Heliyon, 2018 During the last 40 years, many studies have been carried out to investigate the different phenomena occurring during a Severe Accident (SA) in a Nuclear Power Plant (NPP).
Bruno Gonfiotti, Sandro Paci
doaj +2 more sources
Thermal hydraulic analysis and estimation of hydrogen generation in severe accidents in WWER1000 [PDF]
مجله علوم و فنون هستهای, 2022 Severe Accidents Management (SAM) in nuclear power plants is an important safety issue. SAMs require assessing the thermal-hydraulic conditions of the nuclear reactor during the accident.
R. Gharari +4 more
doaj +1 more source
Energies, 2021 The paper presents a study of the critical flow phenomena modeling with MELCOR 2.2.15254 severe accident computer code. The Marviken Critical Flow Test number 21 (CFT-21) experiment was selected as a representative critical flow-focused Separate Effect ...
Mateusz Włostowski +2 more
doaj +1 more source
Impact of PSI-KIT Nitriding model on hypothetical Spent Fuel Pool accident simulation
Nuclear Engineering and Technology, 2023 In past years the Paul Scherrer Institute (PSI, Switzerland) and the Karlsruhe Institue of Technology (KIT, Germany)) collaborated to develop a model to account for the active role of nitrogen in the air oxidation of a Zircalloy cladding.
Mateusz Malicki, Terttaliisa Lind
doaj +1 more source
Thermal-hydraulic analysis of loss-of-cooling accident in spent fuel pool of Bushehr NPP using the RELAP5 and MELCOR [PDF]
مجله علوم و فنون هستهای, 2020 Following the Fukushima Daiichi accident, the simulation of accidents related to the Spent Fuel Pool (SFP) became more important due to the high content of long-lived radionuclides, and lack of the protection by the pressure vessel despite its low decay ...
S. Gol Narges, S.Kh. Mousavian
doaj +1 more source
Investigation on Aerosol Pool Scrubbing Model During Severe Accidents
Frontiers in Energy Research, 2021 During a nuclear power plant severe accident, discharging gas mixture into the spent-fuel pool is an alternative containment depressurization measurement through which radioactive aerosols can be scrubbed.
L. W. He +5 more
doaj +1 more source