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

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5 Author(s)

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

Published in:

Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium  (Volume:1 )

Date of Conference:

30 Sep-5 Oct 1995

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