Title :
Selection of plasma facing materials for ITER
Author :
Ulrickson, M. ; Barabash, V. ; Chiocchio, S. ; Federici, G. ; Janeschitz, G. ; Matera, R. ; Akiba, M. ; Vieider, G. ; Wu, C. ; Mazul, I.
Author_Institution :
Sandia Nat. Labs., Albuquerque, NM, USA
fDate :
30 Sep-5 Oct 1995
Abstract :
ITER will be the first tokamak having long pulse operation using deuterium-tritium fuel. The problem of designing heat removal structures for steady state in a neutron environment is a major technical goal for the ITER Engineering Design Activity (EDA). The steady state heat flux specified for divertor components is 5 MW/m2 for normal operation with transients to 15 MW/m2 for up to 10 s. The selection of materials for plasma facing components is one of the major research activities. Three materials are being considered for the divertor; carbon fiber composites, beryllium, and tungsten. This paper discusses the relative advantages and disadvantages of these materials. The final selection of plasma facing materials for the ITER divertor will not be made until the end of the EDA
Keywords :
fusion reactor design; fusion reactor materials; fusion reactors; 10 s; Be; C fiber composites; DT; DT fuel; Engineering Design Activity; ITER; W; divertor components; fusion reactors; heat removal structures; long pulse operation; neutron environment; normal operation; plasma facing materials; steady state; steady state heat flux; tokamak; Composite materials; Design engineering; Electronic design automation and methodology; Fuels; Heat engines; Neutrons; Organic materials; Plasma materials processing; Steady-state; Tokamaks;
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
DOI :
10.1109/FUSION.1995.534250
