IN-VESSEL TRANSIENT ANALYSIS CODE INTRA FOR ITER ACCIDENT ANALYSES

The INTRA code is being developed to analyse integrated behaviours suc h as pressurisation, chemical reactions and temperature transients in case of accidents inside the plasma chamber and adjacent rooms of ITER . INTRA is based on the results of extensive research on containment s afety analysis work for fission nuclear power plants. It is derived fr om the code RALOC, which was validated on a large scale and used in li censing procedures. INTRA is specified as an ITER reference code for i n-vessel reactions and transport and distribution modelling within the vacuum vessel and its surroundings. First comparisons of INTRA calcul ations with the Japanese ICE/LOVA experiment shows good agreement. Res ults from one of the ITER category TV reference accident sequences als o indicate, by inter code comparisons with the MELCOR code, that INTRA will be an important code for NSSR-2 analyses. (C) 1998 Elsevier Scie nce S.A. All rights reserved.