• Title of article

    ASTEC and ICARE/CATHARE modelling improvement for VVERs

  • Author/Authors

    S.V. Zvonarev، نويسنده , , Yu and Volchek، نويسنده , , A. and Kobzar، نويسنده , , V. and Chatelard، نويسنده , , P. and Van Dorsselaere، نويسنده , , J.P.، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2011
  • Pages
    8
  • From page
    1055
  • To page
    1062
  • Abstract
    ASTEC and ICARE/CATHARE computer codes, developed by IRSN (France) (the former with GRS, Germany), are used in RRC KI (Russia) for the analyses of accident transients on VVER-type NPPs. The latest versions of the codes were continuously improved and validated to provide a better understanding of the main processes during hypothetical severe accidents on VVERs. aper describes modelling improvements for VVERs carried out recently in the ICARE common part of the above codes. These actions concern the important models of fuel rod cladding mechanical behaviour and oxidation in steam at high and very high temperatures. The existing models were improved basing on the experience in the field and latest literature data sources for Zr + 1%Nb material used for manufacture of VVERs fuel rod claddings. itted correlations for the Zr alloy oxidation through a broad temperature range were established, along with recommendations on model application in clad geometry and starvation conditions. A model for the creep velocity was chosen for the clad mechanical model and some cladding burst criteria were established as a function of temperature. verification of modelling improvements on Separate Effect Tests, validation was carried out on integral bundle tests such as QUENCH, CODEX-CT, PARAMETER-SF (the application to the CORA-VVER experiments is not described in the present paper) and on the Paks-2 cleaning tank incident. The comparison of updated code results with experimental data demonstrated very good numerical predictions, which increases the level of code applicability to VVER-type materials.
  • Journal title
    Nuclear Engineering and Design Eslah
  • Serial Year
    2011
  • Journal title
    Nuclear Engineering and Design Eslah
  • Record number

    1590577