Thermodynamic evaluation of the solidification phase of molten core–concrete under estimated Fukushima Daiichi nuclear power plant accident conditions
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- Type
- article
- Published
- 2017-04-01
- Cited by
- 36
- References
- 25
- OpenAlex
- https://openalex.org/W2579882074
- Semantic Scholar
- https://api.semanticscholar.org/CorpusID:99973671
Keywords
Corium, Materials science, Quenching (fluorescence), Nuclear power plant, Core (optical fiber)
References
- Nuclear Safety in Light Water Reactors : Severe Accident Phenomenology
- TMI-2 core debris grab samples: Examination and analysis: Part 2
- Simulation of MCCI with the TOLBIAC-ICB code based on the phase segregation model
- European validation of the integral code ASTEC (EVITA)
- Thermo-physical properties and transient heat transfer of concrete at elevated temperatures
- A study on concrete degradation during molten core/concrete interactions
- Microstructure of plasma dissociated zircon and liquid immiscibility in the ZrO2-SiO2 system
- Dissolution behavior of (U,Zr)O2-based simulated fuel debris in nitric acid
- Two-dimensional interaction of oxidic corium with concretes: The VULCANO VB test series
- Experiments on MCCI with oxide and steel
- The calculation of phase equilibria of oxide core-concrete systems
- Physico-chemical analyses and solidification path reconstruction of multi-component oxidic spread melts
- Steel oxidation phenomena during Molten Corium siliceous Concrete Interaction (MCCI)
- Phase segregation model and molten pool thermal-hydraulics during molten core-concrete interaction
- Chemical thermodynamic representation of
- Direction on characterization of fuel debris for defueling process in Fukushima Daiichi Nuclear Power Station
- FactSage thermochemical software and databases, 2010–2016
- Study of the mixing of immiscible liquids by sparging gas - results of the BALISE experiments
- 2.25 – Core Concrete Interaction
Cited by
- Materials and design concepts for space-resilient structures
- Study on the leaching behavior of actinides from nuclear fuel debris
- Fiber-optic laser-induced breakdown spectroscopy of zirconium metal in air: Special features of the plasma produced by a long-pulse laser
- Fukushima Daiichi fuel debris simulant materials for the development of cutting and collection technologies
- Phase analysis of uranium oxides after reaction with stainless steel components and ZrO2 at high temperature by XRD, XAFS, and SEM/EDX
- Effect of quenching on molten core-concrete interaction product
- Leaching behavior of gamma-emitting fission products, calcium, and uranium from simulated MCCI debris in water
- Study on the chemical structure and actinide leaching of MCCI debris
- Chemical forms of uranium evaluated by thermodynamic calculation associated with distribution of core materials in the damaged reactor pressure vessel
- Development of microwave-enhanced fibre-coupled laser-induced breakdown spectroscopy for nuclear fuel debris screening at Fukushima
- Experimental evaluation of Sr and Ba distribution in ex-vessel debris under a temperature gradient
- Safely probing the chemistry of Chernobyl nuclear fuel using micro-focus X-ray analysis
- Mechanical properties and thermal conductivity of (U,Zr)SiO4
- Corium Experimental Thermodynamics: A Review and Some Perspectives
- Evaluation of the dissolution behavior of zircon using high-resolution phase-shift interferometry microscope
- High-temperature mechanical properties of low-carbon steel used for the manufacture of core catcher vessel
- Chemical characterisation of degraded nuclear fuel analogues simulating the Fukushima Daiichi nuclear accident
- Dissolution and precipitation behaviors of zircon under the atmospheric environment
- First-principles investigations on the interface structure, stability and electronic properties of UN/ZrC for dispersion nuclear fuel
- Experimental Cutting of Snf Samples by Mechanical and Thermal Methods to Examine the Efficiency of Different Air Filtration Techniques of Generated Dust
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