Results 211 to 220 of about 401 (227)
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Nuclear Engineering and Design, 2015
Abstract During an hypothetical Pressurized Water Reactor (PWR) or Boiling Water Reactor (BWR) severe accident with core meltdown and vessel failure, corium would fall directly on the concrete reactor pit basemat if no water is present. The high temperature of the corium pool maintained by the residual power would lead to the erosion of the concrete ...
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Abstract During an hypothetical Pressurized Water Reactor (PWR) or Boiling Water Reactor (BWR) severe accident with core meltdown and vessel failure, corium would fall directly on the concrete reactor pit basemat if no water is present. The high temperature of the corium pool maintained by the residual power would lead to the erosion of the concrete ...
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Numerical investigation of convection heat transfer characteristics in sloshing corium pools
Nuclear Engineering and Design, 2022Jiajia Deng +5 more
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Experimental study of stratification behavior of the steady two-liquid corium pool
Nuclear Engineering and Design, 2022Baoquan Xue +8 more
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Analysis of Transient Corium Pool Structure in the Lower Plenum of Reactor Vessel
2021RONG CAI, Lili Liu, Liang Chen
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Corium pool behaviour in the core catcher of a sodium-cooled fast reactor
Nuclear Engineering and Design, 2023Rémi Clavier +2 more
exaly
20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20), 2023
D. Dovizio, Ed Komen
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D. Dovizio, Ed Komen
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Heat transfer behaviors in corium pools under swinging conditions
Applied Thermal EngineeringSimin Luo, Peng Chen
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