Title :
Nuclear analysis in support of the design of ITER blanket modules
Author :
Sawan, Mohamed E.
Author_Institution :
Fusion Technol. Inst., Univ. of Wisconsin-Madison, Madison, WI, USA
Abstract :
Detailed profiles of nuclear heating and radiation damage parameters were determined in ITER blanket modules at different poloidal locations. The results indicate that the nuclear parameters are sensitive to the configuration and material composition with enhanced steel heating and helium production in regions with large water content.
Keywords :
CAD; Tokamak devices; fusion reactor blankets; fusion reactor design; heat treatment; nuclear engineering computing; plasma toroidal confinement; radiation effects; ITER blanket module design; helium production; nuclear analysis; nuclear heating parameters; nuclear parameters; poloidal locations; radiation damage parameters; steel heating; Heating; Loading; Materials; ITER; blanket; nuclear heating; radiation damage;
Conference_Titel :
Fusion Engineering (SOFE), 2011 IEEE/NPSS 24th Symposium on
Conference_Location :
Chicago, IL
Print_ISBN :
978-1-4577-0669-1
Electronic_ISBN :
1078-8891
DOI :
10.1109/SOFE.2011.6052350
