Title :
Nuclear heating and damage profiles in the ITER divertor cassette
Author :
Sawan, M.E. ; Santoro, R.T.
Author_Institution :
Fusion Technol. Inst., Wisconsin Univ., Madison, WI, USA
Abstract :
Three-dimensional neutronics calculations have been performed to determine the detailed spatial distribution of the nuclear parameters in the divertor cassettes used in ITER. These parameters included power density, atomic displacement and helium production. The largest heating and damage occurs in the dome which has full view of the plasma. The power density in the tungsten plasma facing material at the dome is 16.4 W/cm3. The total nuclear heating in the 60 divertor cassettes is 101.6 MW with the major contributors being the dome, vertical targets, and wings
Keywords :
fusion reactor design; fusion reactor ignition; fusion reactor operation; neutron flux; plasma heating; plasma toroidal confinement; 101.6 MW; 3D neutronics calculations; He; He production; ITER divertor cassette; W; atomic displacement; damage profiles; fusion reactors; nuclear heating; plasma; power density; spatial distribution; vertical targets; wings; Coils; Composite materials; Coolants; Ducts; Heating; Helium; Plasma density; Plasma materials processing; Production; Tungsten;
Conference_Titel :
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Conference_Location :
San Diego, CA
Print_ISBN :
0-7803-4226-7
DOI :
10.1109/FUSION.1997.687754
