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Radiochimica Acta, ISSN 0033-8230, 11/2019, Volume 107, Issue 12, pp. 1155 - 1160
Samples of Chernobyl fuel debris such as corium and “lava” had been studied using repeated static leach test MCC-1 at temperature of 25 and 90 °C in distilled... 
cesium-137 | Chernobyl | corium | Leaching | fuel debris
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 04/2020, Volume 138, p. 107166
During a core meltdown accident, the significant decay heat within the corium pool will continually impose thermal load on the vessel wall and challenge the... 
Corium pool | Natural convection | Two-layer | COPRA
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 01/2020, Volume 135, p. 107004
During a severe accident in a nuclear reactor, core damage occurs and may lead to the formation of corium, followed by relocation to the vessel lower head. The... 
CFD | Natural convection | Severe accident | Corium pools | TURBULENT NATURAL-CONVECTION | HEAT-TRANSFER | NUCLEAR SCIENCE & TECHNOLOGY | POOLS | PRANDTL-NUMBER | CORIUM
Journal Article
Progress in Nuclear Energy, ISSN 0149-1970, 11/2016, Volume 93, pp. 297 - 305
An experimental research platform using corium melts is established for the understanding of safety related important phenomena during a severe accident... 
Steam explosion | Cold crucible | Corium | Corium structural material interaction | Ablation | VESSEL STEEL | UO2/ZRO2 MIXTURE | NUCLEAR SCIENCE & TECHNOLOGY | MODEL DEVELOPMENT | MOLTEN CORIUM | CORROSION | Nuclear energy | Usage | Nickel alloys | Building materials | Investigations | Research institutes | Accidents
Journal Article
Applied Thermal Engineering, ISSN 1359-4311, 12/2018, Volume 145, pp. 38 - 47
The Large Eddy Simulation (LES) methods were employed to analyze the turbulent heat transfer characteristics in detail for volumetrically heated corium pools.... 
Corium pool | WMLES | IVR | Heat transfer | Layer instability | VESSEL | MELT POOL | VORTICES | ENERGY & FUELS | RAYLEIGH NUMBERS | MOLTEN CORIUM | MODEL | CONVECTION HEAT-TRANSFER | ENGINEERING, MECHANICAL | MECHANICS | THERMODYNAMICS | COPRA EXPERIMENTS | LES | Turbulence | Models | Numerical analysis | Analysis
Journal Article
Journal of Nuclear Materials, ISSN 0022-3115, 02/2020, Volume 529, p. 151918
Journal Article
Applied Thermal Engineering, ISSN 1359-4311, 06/2019, Volume 156, pp. 730 - 740
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 01/2018, Volume 111, pp. 293 - 302
Due to the high-Rayleigh-number natural convection and strong turbulence in the volumetrically heated corium melt pools, it is difficult to capture the heat... 
Corium pool | Large eddy simulation | Turbulent heat transfer | IVR | NATURAL-CONVECTION | MELT POOL | RETENTION | BEHAVIOR | LIVE EXPERIMENTS | SOLIDIFICATION | MOLTEN CORIUM | NUCLEAR SCIENCE & TECHNOLOGY | COOLABILITY | COPRA EXPERIMENTS | EFFECTIVE CONVECTIVITY MODEL | Analysis | Numerical analysis | Nuclear industry | Nuclear energy
Journal Article
Nuclear Engineering and Design, ISSN 0029-5493, 11/2012, Volume 252, pp. 184 - 191
► We investigate CHF limits of graphene-oxide nanofluids for IVR-ERVC. ► Graphene-oxide nanofluids were stable under ERVC coolant chemical environments. ► GO... 
COOLABILITY | SURFACE | NUCLEAR SCIENCE & TECHNOLOGY | IN-VESSEL RETENTION | CORIUM | WATER | Heart failure | Nanotechnology
Journal Article
Âderna Fìzika ta Energetika, ISSN 1818-331X, 05/2018, Volume 13, Issue 1, pp. 62 - 72
Paper is devoted to the development of the mathematical model and analysis of the problem of corium melt interaction with low-temperature melting blocks in the... 
coolability | solidification | model | corium | melting blocks
Journal Article
RADIOCHIMICA ACTA, ISSN 0033-8230, 12/2019, Volume 107, Issue 12, pp. 1155 - 1160
Samples of Chernobyl fuel debris such as corium and "lava" had been studied using repeated static leach test MCC-1 at temperature of 25 and 90 degrees C in... 
cesium-137 | Chernobyl | NUCLEAR SCIENCE & TECHNOLOGY | corium | Leaching | fuel debris | CHEMISTRY, INORGANIC & NUCLEAR
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 06/2020, Volume 141, p. 107266
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 01/2016, Volume 87, Issue 2, pp. 81 - 88
Large scale COPRA experiments were performed to study the natural convection heat transfer in corium pools inside the reactor pressure vessel lower plenum... 
Corium pool | Natural convection | Severe accident | IVR | COPRA | MODULE | MELT | NUCLEAR SCIENCE & TECHNOLOGY | IN-VESSEL RETENTION | ANALYSIS CODE MIDAC | CORIUM | Heating | Nuclear reactor components | Nuclear power generation | Nuclear reactors | Pools | Heat flux | Heat transfer | Accidents
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 11/2019, Volume 133, pp. 359 - 377
The worst event that could happen in a nuclear power plant is a severe accident. If during such accident the corium melt comes into contact with the coolant... 
MC3D computer code | Steam explosion | Severe accident | Simulation | Premixing | Oxidation | Corium | CHALLENGE | NUCLEAR SCIENCE & TECHNOLOGY
Journal Article
Nuclear Engineering and Design, ISSN 0029-5493, 12/2019, Volume 355, p. 110271
In the framework of the European IVMR project, dedicated to the assessment of In-Vessel Retention (IVR) strategy for high power reactors, VITI-CORMET tests,... 
Suboxidized solid corium | Molten stainless steel | In-Vessel Retention | Focusing effect | DISSOLUTION | NUCLEAR SCIENCE & TECHNOLOGY | POOL
Journal Article
Nuclear Technology, ISSN 0029-5450, 11/2019, Volume 205, Issue 11, pp. 1488 - 1494
Finite element analysis is used to study heat transfer from a corium pool at the bottom of the calandria to its surroundings during a severe accident in a... 
CANDU severe accident | in-vessel retention | REACTOR VESSEL | NUCLEAR SCIENCE & TECHNOLOGY | SEVERE ACCIDENT | CORIUM | WATER
Journal Article
Nuclear Technology, ISSN 0029-5450, 12/2011, Volume 176, Issue 3, pp. 372 - 386
Three triggered steam explosion experiments were performed in the TROI facility with a two-dimensional interaction vessel of 0.6-m diameter. The melt... 
Corium | Steam explosion | TROI | KROTOS | NUCLEAR SCIENCE & TECHNOLOGY | steam explosion | FUEL | corium | COOLANT INTERACTION EXPERIMENTS | PARTIALLY OXIDIZED CORIUM
Journal Article
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