Results 71 to 80 of about 1,365 (205)
Science and Technology of Nuclear Installations, 2014 Distances for taking evacuation as a protective measure during early phase of a nuclear accident have been approximated using MELCOR Accident Consequence Code System (MACCS).
Mazzammal Hussain +3 more
doaj +1 more source
Melcor Benchmarking Against Integral Severe Fuel Damage Tests [PDF]
, 1994 MELCOR is a fully integrated computer code that models all phases of the progression of severe accidents in light water reactor nuclear power plants, and is being developed for the US Nuclear Regulatory Commission (NRC) by Sandia National Laboratories ...
Madni, I.K.
core
, 2015 Several incidental/accidental conditions can hamper the safety of a fusion reactor, and the Loss of Coolant Accident (LOCA) of the blanket Primary Heat Transfer System (PHTS) is one of the most challenging [1].
GONFIOTTI, BRUNO +2 more
core
MELCOR Capability Development for Simulation of Debris Bed Coolability
, 2021 The severe accident management (SAM) strategy for a Nordic boiling water reactor (BWR) employs cavity flooding prior to vessel failure, so that the core melt (corium) discharged from the vessel could fragment and form a particulate debris bed. The key to
Chen, Yangli
core +2 more sources
Progress on the MELCOR code [PDF]
, 1995 Sandia has made considerable progress in the past year on the MELCOR code for integrated severe nuclear reactor accident analysis.
Bergeron, K. +5 more
core
Modifications made to the MELCOR Code for Analyzing Lithium Fires in Fusion Reactors [PDF]
, 2000 This report documents initial modifications made to the MELCOR code that allows MELCOR to predict the consequences of lithium spill accidents for evolving fusion reactor designs.
Merrill, Brad Johnson, Merrill, B. J.
core +1 more source
Modeling of PANDA isolation condenser experiments with MELCOR and Apros
, 2020 Modeling methods were developed for passive cooling systems, in which steam condenses in vertical tubes. Isolation condenser experiments performed in the PANDA facility were calculated with two computer codes: the severe accident code MELCOR, and the ...
Sevón, Tuomo; id_orcid, Hillberg, Seppo
core +1 more source
MELCOR 1.8.3 assessment: CSE containment spray experiments [PDF]
, 1994 MELCOR is a fully integrated, engineering-level computer code, being developed at Sandia National Laboratories for the USNRC, that models the entire spectrum of severe accident phenomena in a unified framework for both BWRs and PWRS.
Kmetyk, L. N.
core +1 more source
Nuclear Engineering and TechnologyA reliable prediction on the behavior of source terms is essential for devising effective accident response measures to cope with the severe accident of a nuclear power plant.
Han Sol Park +3 more
doaj +1 more source
MELCOR technical assessment at SNL
, 1993 MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor (LWR) nuclear power plants, which is being developed at Sandia National Laboratories for the US Nuclear Regulatory ...
Kmetyk, L. N., Tautges, T. J.
core