Русский / English 
NUCLEAR SAFETY INSTITUTE OF THE
RUSSIAN ACADEMY OF SCIENCES
INSTITUTERESEARCHPROJECTSSCIENCE AND EDUCATIONNEWSCONTACTS
 

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.



DOWNLOAD »


IBRAE RAN © 2013-2024 Site map | Feedback