Direct Containment Heating Investigations for European Pressurized Water Reactors (original) (raw)
Investigations of Direct Containment Heating (DCH) in European Reactors: Database of Integral Tests and Progress in Modeling
Leonhard Meyer
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The 15 th International Topical Meeting on Nuclear Reactor Thermal -Hydraulics, NURETH-15 PRELIMINARY ASSESSMENT OF THE THERMAL INTERACTION AMONG CORIUM AND IN-VESSEL CORE CATCHER IN A LARGE SODIUM FAST REACTOR
Flavio Parozzi
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Corium Dispersion and Direct Containment Heating Experiments at Low System Pressure
Leonhard Meyer
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Experiments to investigate direct containment heating phenomena with scaled models of the Surry Nuclear Power Plant
Martin Pilch
1994
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Evaluation of CFD Capability for Simulation of Energetic Flow in Light Water Reactor Containment
Nam Dinh
2015
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Ex-Vessel Corium Coolability and Steam Explosion Energetics in Nordic Light Water Reactors
Nam Dinh
2008
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Experimental results of direct containment heating by high-pressure melt ejection into the Surtsey vessel: The DCH-3 and DCH-4 tests
John Brockmann
1991
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An approach to numerical simulation and analysis of molten corium coolability in a boiling water reactor lower head
P. Kudinov
2010
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Melt Dispersion and Direct Containment Heating (DCH) Experiments in the DISCO-H Test Facility
Leonhard Meyer
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Modeling of corium melt cooling during severe accidents at the nuclear power plants
Ivan Kazachkov
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Separate Effects Tests on Hydrogen Combustion during Direct Containment Heating Events in European Reactors
Leonhard Meyer
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LIVE Experiments on Melt Behavior in the Reactor Pressure Vessel Lower Head
Major Major
Heat Transfer Engineering, 2013
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Evaluation of heat-flux distribution at the inner and outer reactor vessel walls under the in-vessel retention through external reactor vessel cooling condition
Sang Ho An
Nuclear Engineering and Technology, 2015
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Test results on direct containment heating by high-pressure melt ejection into the Surtsey vessel: The TDS test series
Martin Pilch
1994
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Experimental simulation of corium dispersion phenomena in direct containment heating
Shripad Revankar
Nuclear Engineering and Design, 1996
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Cooling of molten core material within a pressurised water reactor vessel lower head: interaction of surface radiation and wall conduction with free convection
A. Cihat Baytaş
International Journal of Engineering Science, 2001
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Plant application of ICARE/ASTECv2.0r3 computer code for investigation of in-vessel melt retention in VVER-1000 reactor design
Pavlin Groudev
Annals of Nuclear Energy, 2015
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Study of the processes of corium-melt retention in the reactor pressure vessel (INVECOR)
Christophe Journeau
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Preliminary Assessment of the Thermal Interaction Among Corium and In-Vessel Core Catcher in a Large Sodium Fast Reactor
Giovanni Manzini
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High pressure simulation experiment on corium dispersion in direct containment heating
Shripad Revankar
Nuclear Engineering and Design, 1996
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Improved thermal hydraulic analyses of nuclear reactor and containment (THARE). THARE summary report
Jarto Niemi
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Modelling of heat and mass transfer processes during core melt discharge from a reactor pressure vessel
Nam Dinh
Nuclear Engineering and Design, 1996
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Modelling of Severe Accident and In-Vessel Melt Retention Possibilities in BWR Type Reactor
Algirdas Kaliatka
Science and Technology of Nuclear Installations, 2018
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Assessment of passive containment cooling concepts for advanced pressurized water reactors
Won-Pil Baek
Annals of Nuclear Energy, 1997
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The influence of the water ingression and melt eruption model on the MELCOR code prediction of molten corium-concrete interaction in the APR-1400 reactor cavity
Muritala A Amidu
Nuclear Engineering and Technology
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The 15 th International Topical Meeting on Nuclear Reactor Thermalhydraulics, NURETH-15 PRELIMINARY EVALUATION OF THERMAL-HYDRAULICS BLOCKAGE EVENTS IN A OPEN SQUARE CORE DESIGN FOR A LFR REACTOR
Paride Meloni, S. Manservisi
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Modeling of the Reactor Core Isolation Cooling Response to Beyond Design Basis Operations - Interim Report
Randall Gauntt
2015
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Containment behaviour in the event of core melt with gaseous and aerosol releases (CONGA
Salih Guentay
Nuclear Engineering and Design, 2001
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Thermal Hydraulic Analysis in Reactor Vessel Internals Considering Irradiation Heat
Kunwoo Yi
2015
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Thermal-Hydraulic Analysis of Nuclear Reactors
Mostafijur RAHMAN Kazi
2015
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Corium behavior and steam explosion risks: A review of experiments
Christophe Journeau
Annals of Nuclear Energy, 2018
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Results of an experiment in a Zion-like geometry to investigate the effect of water on the containment basement floor on direct containment heating (DCH) in the Surtsey Test Facility: The IET-4 test
Martin Pilch
1992
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Thermal hydraulic considerations of nuclear reactor systems: Past, present and future challenges
Minhajur Rahman
Experimental and Computational Multiphase Flow
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Convective cooling in a pool-type research reactor
Shoaib Usman
2016
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Simulation of Core Melt Pool Formation in a Reactor Pressure Vessel Lower Head Using an Effective Convectivity Model
Nam Dinh
Nuclear Engineering and Technology, 2009
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