2.25 – Core Concrete Interaction
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- Published
- 2012-01-01
- Cited by
- 15
- References
- 46
- Semantic Scholar
- https://api.semanticscholar.org/CorpusID:137957544
References
- Study of void fraction and mixing of immiscible liquids in a pool configuration by an upward gas flow
- Hydrodynamics and heat transfer characteristics of liquid pools with bubble agitation
- Modeling of ex-vessel corium coolability with the CORQUENCH code.
- Enhancement of heat transfer between two horizontal liquid layers by gas injection at the bottom
- European Experiments on 2-D Molten Core Concrete Interaction: HECLA and VULCANO
- Model description and user's manual
- Assessment of Two-Phase Flow Heat Transfer Correlations for Molten Core-Concrete Interaction Study
- Solidus and liquidus temperatures of core-concrete mixtures
- BOILING AND BUBBLING HEAT TRANSFER UNDER THE CONDITIONS OF FREE AND FORCED CONVECTION
- Core-concrete interactions using molten steel with zirconium on a basaltic basemat: The SURC-4 experiment
- An improved interface model for molten corium–concrete interaction
- Ex-vessel corium spreading: results from the VULCANO spreading tests
- Convection heat transfer anisotropy in a bubbling viscous pool-Application to molten core-concrete interaction
- Improvement of the European thermodynamic database NUCLEA
- Corium viscosity modelling above liquidus temperature
- The use of thermal analysis in assessing the effect of temperature on a cement paste
- Rheological Transitions During Partial Melting and Crystallization with Application to Felsic Magma Segregation and Transfer
- Viscosity models for corium melts
- A heat transfer analysis of the CCI experiments 1-3
- Simulation of MCCI with the TOLBIAC-ICB code based on the phase segregation model
Cited by
- Experimental contribution to the corium thermodynamic modelling – The U–Zr–Al–Ca–Si–O system
- Thermodynamic evaluation of the solidification phase of molten core–concrete under estimated Fukushima Daiichi nuclear power plant accident conditions
- A review on hydrogen generation, explosion, and mitigation during severe accidents in light water nuclear reactors
- Fukushima Daiichi fuel debris simulant materials for the development of cutting and collection technologies
- Comparative study on the thermal behavior of structural concretes of sodium-cooled fast reactor
- Effect of quenching on molten core-concrete interaction product
- Material characterization of the VULCANO corium concrete interaction test with concrete representative of Fukushima Daiichi Nuclear Plants
- Radiative Heat Exchange in a Gas Cavity Above Reactor Core Melt During a Serious Accident
- A preliminary study on concrete ablation during ex-vessel cooling in pre-flooded Westinghouse 3-loop NPP reactor cavity
- Evaluation of the dissolution behavior of zircon using high-resolution phase-shift interferometry microscope
- Thermodynamic Analysis for Solidification Path of Simulated Ex-Vessel Corium
- Investigation of prototypical corium interaction with samples of VVER-1000 in-vessel and ex-vessel structures
- Refractory geopolymers: Thermal shock resistant material for nuclear safety
- A Review on Ex-Vessel Melt Retention Measures Adopted in Light Water Reactors
- Study on criticality uncertainties of MCCI products due to concrete compositions
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