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Prandtl number effect on thermal behavior in volumetrically heated pool in the high Rayleigh number region
- Source :
- Nuclear Engineering and Design. 351:72-79
- Publication Year :
- 2019
- Publisher :
- Elsevier BV, 2019.
-
Abstract
- The in-vessel retention by external reactor vessel cooling (IVR-ERVC) is a severe accident management strategy to hold or mitigate the molten radioactive material in the reactor pressure vessel (RPV). Highly turbulent natural convection is one of the most important phenomenon determining the thermal behavior of the molten pool. In the safety evaluation of IVR-ERVC, thermal behavior of the corium pool has been determined using experimental correlations. Property differences between the experimental simulant and the corium have been considered negligible. The effect of property differences represented by Prandtl number (Pr) on the thermal behavior of oxide pool is numerically investigated. The algebraic heat flux model (AFM) is used to simulate the turbulent natural convection and is validated with the BALI experiment. The Pr effect on the flow characteristics and the thermal behavior is investigated in the high Rayleigh number region. The present results show that the upward heat transfer tends to increase at the same Ra ′ in the case of the molten pool which is lower Pr fluid than the simulant material.
- Subjects :
- Nuclear and High Energy Physics
Materials science
Mechanical Engineering
Prandtl number
Flow (psychology)
Rayleigh number
Mechanics
Corium
Physics::Fluid Dynamics
symbols.namesake
Nuclear Energy and Engineering
Heat flux
Heat transfer
Thermal
symbols
General Materials Science
Safety, Risk, Reliability and Quality
Waste Management and Disposal
Reactor pressure vessel
Subjects
Details
- ISSN :
- 00295493
- Volume :
- 351
- Database :
- OpenAIRE
- Journal :
- Nuclear Engineering and Design
- Accession number :
- edsair.doi...........846f075feabe75a695eed7aa9628e411
- Full Text :
- https://doi.org/10.1016/j.nucengdes.2019.05.007