Nuclear-thermal coupled calculation of a shielding blanket for an experimental fusion reactor

摘要

To obtain accurate time-dependent temperature distribution in fusion reactor nuclear components, a nuclear-thermal coupled calculation code system has been developed. The code system couples the two-dimensional radiation transport code DOT-3.5 and a finite element non-linear temperature analysis code ADINAT. Using this code system, the time-dependent temperature distribution in a shielding blanket of a fusion experimental reactor similar to ITER has been calculated for various conditions. The code system has been further extended to calculate thermal stress, by coupling the structural analysis code ADINA.