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

Author

Seki, Yasushi ; Kurihara, Ryoichi ; Ueda, Shuzo ; Sugaya, Shinichi ; Kawasaki, Hiromitsu

Author_Institution

JAERI, Ibaraki, Japan

Volume

1

fYear

1995

fDate

30 Sep-5 Oct 1995

Firstpage

361

Abstract

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

Keywords

finite element analysis; fusion reactor blankets; fusion reactor design; fusion reactor safety; nuclear engineering computing; shielding; temperature distribution; thermal stresses; 2D radiation transport code; ADINA code; ADINAT code; DOT-3.5; ITER; experimental fusion reactor; finite element nonlinear temperature analysis; nuclear components; nuclear-thermal coupled calculation; nuclear-thermal coupled calculation code; shielding blanket; structural analysis code; thermal stress; time-dependent temperature distribution; Finite element methods; Fusion reactor design; Fusion reactors; Heating; Inductors; Neutrons; Plasma temperature; Steady-state; Temperature distribution; Thermal stresses;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium

Conference_Location

Champaign, IL

Print_ISBN

0-7803-2969-4

Type

conf

DOI

10.1109/FUSION.1995.534242

Filename

534242