Socrat Code: Evaluation for Modeling the Destruction of RBMK Fuel Channels during Serious Accidents

The SOCRAT computational code was developed and is used for modeling serious accidents at NPP. The present article analyzes the possibility of using the physicochemical models implemented in the SOCRAT code to calculate the processes arising in an RBMK-1000 core during serious accidents. It is shown...

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Veröffentlicht in:Atomic energy (New York, N.Y.) N.Y.), 2014-02, Vol.115 (4), p.253-259
Hauptverfasser: Dolganov, K. S., Kiselev, A. E., Yudina, T. A., Nikitin, Yu. M.
Format: Artikel
Sprache:eng
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Zusammenfassung:The SOCRAT computational code was developed and is used for modeling serious accidents at NPP. The present article analyzes the possibility of using the physicochemical models implemented in the SOCRAT code to calculate the processes arising in an RBMK-1000 core during serious accidents. It is shown that the modern version of the code can be used to model the rupture of RBMK fuel assemblies during accidents with complete blackout of a power-generating unit. However, individual models require additional verification under conditions characteristic for RBMK. Particular little-studied processes leading to the destruction of an RBMK core, requiring new models to be developed or extant models adapted for the SOCRAT code, are examined.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-014-9780-9