Is Carbon a Realistic Choice for ITER's Divertor? Page: 3 of 18
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ORNL Workshop on Plasma-Surface Interactions for Fusion
Oak Ridge, Tennessee, March 21-23, 2005.
Submitted to Physica Scripta
Is carbon a realistic choice for ITER's divertor ?
C. H. Skinnera and G. Federicib
a Princeton Plasma Physics Laboratory, Princeton, NJ, USA.
b ITER Garching Joint Work Site, Garching, Germany.
Tritium retention by codeposition with carbon on the divertor target plate is
predicted to limit ITER's DT burning plasma operations (e.g. to about 100 pulses
for the worst conditions) before the in-vessel tritium inventory limit, currently set
at 350 g, is reached. At this point ITER will only be able to continue its burning
plasma program if technology is available that is capable of rapidly removing
large quantities of tritium from the vessel with over 90% efficiency. The removal
rate required is four orders of magnitude faster than that demonstrated in current
tokamaks. Eighteen years after the observation of codeposition on JET and
TFTR, such technology is nowhere in sight. The inexorable conclusion is that
either a major initiative in tritium removal should be funded or that research
priorities for ITER should focus on metal alternatives.
Corresponding author: Charles Skinner email: email@example.com
PACS: 52.40.Hf, 52.55.Fa, 52.90.+z
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Skinner, C.H. & Federici, G. Is Carbon a Realistic Choice for ITER's Divertor?, report, May 13, 2005; Princeton, New Jersey. (https://digital.library.unt.edu/ark:/67531/metadc779415/m1/3/: accessed April 25, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.