Uncertainty Analysis of Vessel Failure Mode and Melt Release in Station Blackout Scenario in Nordic BWR Using MELCOR Code

von Galushin, Sergey
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 3 of 9 (2020)

Effect of Severe Accident Scenario and Modelling Options in MELCOR on the Properties of Relocated Debris in Nordic BWR Lower Plenum

von Galushin, Sergey
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 13 of 14 (2018)

The Effect of Severe Accident Scenarios on In-Vessel Debris Relocation in Nordic BWRs

von Galushin, Sergey
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 3 of 9 (2020)

Comparison of MELCOR code versions Predictions of the Properties of Relocated Debris in Lower Plenum of Nordic BWR

von Galushin, Sergey
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 13 of 14 (2018)

Risk of Containment Failure Due to Ex-Vessel Steam Explosion for Nordic BWRs

von Grishchenko, Dmitry
Veröffentlicht in NURETH (18. : 2019 : Portland, Or.) 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2019 (NURETH 2019) ; Volume 6 of 9 (2020)

Application of Integrated Deterministic-Probabilistic Safety Analysis to Assessment of Severe Accident Management Effectiveness in Nordic BWRs

von Kudinov, Pavel
Veröffentlicht in NURETH (17. : 2017 : Xi'an) 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17) ; Volume 13 of 14 (2018)