A5042063966- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Fusion materials and technologies
- Metallurgical Processes and Thermodynamics
- Thermodynamic and Structural Properties of Metals and Alloys
- Molten salt chemistry and electrochemical processes
- Metallurgy and Material Science
- Nuclear Engineering Thermal-Hydraulics
- Coal Combustion and Slurry Processing
- Material Science and Thermodynamics
- Solidification and crystal growth phenomena
- Material Properties and Failure Mechanisms
- Graphite, nuclear technology, radiation studies
- Engineering Diagnostics and Reliability
- Radioactive element chemistry and processing
- Radiative Heat Transfer Studies
- Nuclear and radioactivity studies
Scientific Research Institute of Technology named after AP Aleksandrov
2021-2022
Research Institute of Technology (Russia)
2009-2020
In the in-vessel corium retention studies conducted on Rasplav-3 test facility within ISTC METCOR-P project and OECD MASCA program, experiments were made to investigate transient processes taking place during oxidation of prototypic molten corium. Qualitative quantitative data have been produced sensitivity melt rate type oxidant, composition, pool surface characteristics. The is a governing factor for additional heat generation hydrogen release; also time secondary inversion oxidic metallic...
During a severe accident with core meltdown, the in-vessel molten retention is challenged by vessel steel ablation due to thermal and physicochemical interaction of melt steel. In accidents oxidizing atmosphere above surface, low melting point UO2+x–ZrO2–FeOy corium pool can form. this case RPV interacting corrosion process. Experiments carried out within International Scientific Technology Center's (ISTC) METCOR Project have shown that rate vary depends on both surface temperature oxygen...
In case of in-vessel corium retention during a severe accident in light water reactor, weakening the vessel wall and deterioration steel properties can be caused both by melting its physicochemical interaction with corium. The behavior has been studied medium-scale experiments prototypic yielded data for corrosion rate UO2+X-ZrO2-FeOy melt air steam at different surface temperatures heat fluxes from to steel. It observed that rates atmosphere are almost same. Further, if temperature...
An experimental study of the melt oxidation kinetics “UO2+x – ZrO2 stainless steel” system by Ar/O2 mixture with an initially superstoichiometric state oxidic part was performed in relation to corium retention reactor vessel (IVR). The tests were absence and partial presence a surface crust on metallic liquid at top position molten pool. It found that specific rate oxidant absorption (oxidation rate) two-liquid oxidic-metallic pool fully oxidized (SS oxidation) suboxidized (Zr U are...