TAILIEUCHUNG - Two- and three-dimensional experiments for oxide pool in in-vessel retention of core melts

The measured Nusselt numbers showed a trend similar to those of existing studies, but the absolute values showed discrepancies owing to the high Prandtl number of this system. The measured angle-dependent Nusselt numbers were analyzed for 2-D and 3-D geometries, and a multiplier was developed that enables the extrapolation of 2-D data into 3-D data. | Two- and three-dimensional experiments for oxide pool in in-vessel retention of core melts Nuclear Engineering and Technology 49 (2017) 1405e1413 Contents lists available at ScienceDirect Nuclear Engineering and Technology journal homepage: Original Article Two- and three-dimensional experiments for oxide pool in in-vessel retention of core melts Su-Hyeon Kim, Hae-Kyun Park, Bum-Jin Chung* Department of Nuclear Engineering, Kyung Hee University, 1732 Deogyeong-daero, Yongin-si, Gyeonggi-do 17104, Republic of Korea a r t i c l e i n f o a b s t r a c t Article history: To investigate the heat loads imposed on a reactor vessel through the natural convection of core melts in Received 10 November 2016 severe accidents, mass transfer experiments were performed based on the heat transfer/mass transfer Received in revised form analogy, using two- (2-D) and three-dimensional (3-D) facilities of various heights. The modified Ray- 10 May 2017 leigh numbers ranged from 1012 to 1015, with a fixed Prandtl number of 2,014. The measured Nusselt Accepted 29 May 2017 Available online 26 June 2017 numbers showed a trend similar to those of existing studies, but the absolute values showed discrep- ancies owing to the high Prandtl number of this system. The measured angle-dependent Nusselt numbers were analyzed for 2-D and 3-D geometries, and a multiplier was developed that enables the Keywords: Correlation extrapolation of 2-D data into 3-D data. The definition of Ra0H was specified for 2-D geometries, so that In-Vessel Retention results could be extrapolated for 3-D geometries; also, heat transfer correlations were developed. Mass Transfer © 2017 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the Multiplier CC BY-NC-ND license (). Natural Convection Oxide Pool 1. Introduction We simulated the IVR .

• Kỹ Thuật - Công Nghệ
• Nuclear engineering and technology
• Two and three dimensional experiments
• Oxide pool in in vessel retention of core melts
• In Vessel Retention
• Facilities of various heights
• The high Prandtl number
• Integral nuclear data validation
• Experimental spent nuclear fuel compositions
• Economic Co operation and Development
• Nuclear Energy Agency
• Nuclear Criticality Safety
• Expanded spent fuel isotopic compositions
• Nuclear reactor vessel water level prediction during severe accidents
• Deep neural networks
• Nuclear power plants
• Maintain nuclear reactor integrity
• Special issue on the International Symposium
• Future Instrumentation and Control for Nuclear Power Plants
• The Nuclear Engineering and Technolog
• Parameter identifiability of Boolean networks
• Application to fault diagnosis of nuclear plants
• Fault diagnosis of nuclear plants
• Nuclear Heating Reactor
• Sensor selection strategy
• Radioactive effluents released from Korean nuclear power plants
• The resulting radiation doses to members of the public
• Korean nuclear power plants
• Nuclear power plant
• The recycling of nuclear graphite after micro oxidation
• Nuclear graphite after micro oxidation
• Whether ground micro oxidation graphite
• The oxidized graphite particles
• The recycling of nuclear graphite
• Statistical model for forecasting uranium prices
• Estimate the nuclear fuel cycle cost
• Nuclear Fuel Cycle Cost
• Nuclear fuel cycle cost calculation
• The statistical autoregressive integrated moving average
• Distinct properties of tungsten austenitic stainless alloy
• Potential nuclear engineering material
• Interchanging the molybdenum in standard SS316 by tungsten
• Gamma and neutron shielding Interchanging the molybdenum
• Nuclear engineering and design
• Brayton cycle
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• Nuclear engineering
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• The base isolated nuclear power plant piping system
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• Nuclear power plant piping system
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• Feasibility study on photo production
• 99mTc with the nuclear resonance fluorescence
• The nuclear resonance fluorescence
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• Sensor fault detection and isolation in a nuclear power plant
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• Surrogate for nuclear fuels fabricated
• Microfluidic sol gel process
• The ceramic nuclear fuel particles
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• Safety system in nuclear power plant
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• Core Damage Assessment
• An evaluation method for nuclear fuel debrisefiltering performance
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• Debris Filtering Performance
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• Development of earthquake instrumentation for shutdown
• Restart criteria of the nuclear power plant
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• The nuclear power plant
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• Six nuclear power plant workers
• Nondestructive inspection of spent nuclear fuel storage canisters
• Shear horizontal guided waves
• Spent nuclear fuel storage canisters
• The cask protecting the canister
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