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NUCLEAR SAFETY INSTITUTE OF THE RUSSIAN ACADEMY OF SCIENCES
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ANALYSIS OF THERMAL INTERACTION BETWEEN THE CORIUM AND SODIUM (PREPRINT IBRAE-2014-01)Language: Русский Publish year: 2014 Pages: 33
| Preprint IBRAE-2014-01
Melikhov V.I., Melikhov O.I., Rtischev N.A., Tarasov A.E.
Analysis of heat transfer processes during a sodium pool boiling is performed. Sodium coolant heat transfer map when it contact with a high temperature corium is prepared. Based on the heat transfer sodium map concluded that the direct contact between the corium surface and liquid sodium or transient heat transfer regime will be occurred, in a typical sodium cooled fast reactors severe accidents conditions. Integral model is developed to simulate thermal interaction between the corium and sodium coolant. Validation results are provided on the base of the THINA (Germany) and PLUTON (Russia) facilities experimental data.
Bibliographical reference
Melikhov V.I., Melikhov O.I., Rtischev N.A., Tarasov A.E. ANALYSIS OF THERMAL INTERACTION BETWEEN THE CORIUM AND SODIUM. Preprint IBRAE-2014-01. Moscow: Nuclear Safety Institute, 2014. 33 p. — Refs.: 39 items.
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