Selection of plasma facing materials for ITER
Ulrickson, M.; Barabash, V.; Chiocchio, S.; Federici, G.; Janeschitz, G.; Matera, R.; Akiba, M.; Vieider, G.; Wu, C.; Mazul, I.
Fusion Engineering, 1995. SOFE apos;95. apos;Seeking a New Energy Eraapos;., 16th IEEE/NPSS Symposium
Volume 1, Issue , 30 Sep-5 Oct 1995 Page(s):394 - 398 vol.1
Digital Object Identifier 10.1109/FUSION.1995.534250
Summary: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
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