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By Kolev, N.

ISBN-10: 0203885767

ISBN-13: 9780203885765

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Additional resources for Multiphase Flow Dynamics 4; Nuclear Thermal Hydraulics

Sample text

427 13. Core degradation ......................................................................................... 1 Processes during the core degradation depending on the structure temperature ............................................................................................ 2 Analytical tools for estimation of the core degradation ......................... 430 References...................................................................................................... 431 14. Melt-coolant interaction ..............................................................................

1 High pressure reduction station.............................................................. 2 Gas release in research reactors piping .................................................. 1 Solubility of O2, N2 and H2 under 1 bar pressure ......................... 2 Some general remarks on the gas release- and absorption dynamics ..................................................................................... 3 Gas release in the siphon safety pipe ..........................................

2 State of the art ........................................................................................ 3 Dry core melting scenario, melt relocation, wall attack, focusing effect ....................................................................................... 4 Model assumptions and brief model description ................................... 1 Molten pool behavior .................................................................. 2 Two dimensional heat conduction through the vessel wall .........

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Multiphase Flow Dynamics 4; Nuclear Thermal Hydraulics by Kolev, N.


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