Recent development and validation of physical models in the computer code INTRA

摘要

The INTRA code is specified by the ITER Joint Central Team and the European Community as a reference code for safety analyses of Tokamak type fusion reactors. The code simulates pressure transients and chemical reactions within the vacuum vessel and surrounding compartments resulting from system failure due to equipment malfunc- tions. During the last year considerable extension and improvements to INTRA have been made.