8th Meeting of the “European MELCOR User Group“

Amec Foster Wheeler, Imperial College London, London, UK
April 6-7, 2016

For information about missing presentations please contact author directly (Please see Agenda and List of Participants)

Title Speaker
Welcome A. Tehrani
Introduction from ICL C. Pain
Introduction from Amec Foster Wheeler M. Turner
Key note address from ONR M. Foy
MELCOR Code Development Status EMUG 2016 L.L. Humphries
Assessment of the Post-Fukushima Improvement of SAM of German PWRs by Severe Accident Analyses T. Steinrötter
MELCOR source term modeling for BWR "Fukushima-like" scenarios with containment venting A. Rýdl
Recent Containment Design Basis Accident Analyses J. Phillips
Particle Depletion in Simplified Geometries J. Kalilainen
MELCOR Application to the Analysis of SMR F. Alcaro
MELCOR Application in the NPP Krško Safety Upgrade Program S. Šadek
Current application of MELCOR 2.1 Code at Bel V M. Adorni
Proof-of-concept Gas Reactor MELCOR Model P. Boneham
Sensitivity Analysis of the Containment venting time of Nordic BWR H. Zhang
Air Oxidation Review of MELCOR Model F. Alcaro
Analyses of Sodium Pool Fire Experiments with MELCOR and ASTEC-CPA Codes F. Mascari
Application of MELCOR 1.8.6 for fusion in comparison with the pedigreed MELCOR 1.8.2 for ITER to simulate DEMO HCPB inbox LOCA X.Z. Jin
Safety assessment of the European Helium-cooled Pebble Bed A. Grief
Helium-cooled Lithium Lead (HCLL) Tritium Breeding Modules S. Owen
Conversion of SFP input deck from MELCOR 1.8.6 to 2.1 and back B.S. Jäckel
MELCOR 1.8.6 Simulation of Severe Accidents Simultaneously Ongoing in the Reactor Core and in the Spent Fuel Pool of the VVER-1000 Type of Reactor M. Kotouč
Spent Fuel Pool (SFP) Loss of Heat Sink Severe Accident calculated by MELCOR and GASFLOW L.G. Horváth
SFP LOCA Analysis with MELCOR F. Alcaro
Safety Analysis of Severe Accident of Spent Fuel Pool Z. Huang
Modelling a Gas Cooled Fast Reactor in MELCOR 2.1 P. Vácha
Announcement of the 9th EMUG meeting in Madrid (Spain) J. Fontanet