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Proceedings Paper

Helium-cooled divertor module for fusion devices
Author(s): Chandrakant B. Baxi
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Paper Abstract

The advanced fusion machines such as TPX, NET, and ITER have to be designed to handle a heat flux of about 5 to 15 MW/m2 in the diverter region. The present conceptual designs use water cooling. However water leaks will have very serious consequences in these machines. Cooling with a gas like helium is a very attractive alternative, if the pumping power can be limited to a reasonable value. Different concepts to cool diverter by helium gas were compared. It was found that it is feasible to remove significant steady state heat flux (10 to 20 MW/m2) by using helium at a pressure of 4 MPa (580 psia) and with pumping power less than 0.5% of the power removed, by using optimized designs. From pumping power consideration, various concepts rank in the following order: offset fins (best), fins, jets, 3-D roughness, 2-D roughness, smooth tubes (worst). A module based on this study has been designed and fabricated for a steady state operation at 10 MW/m2 and was tested at the High Heat Flux facility at Sandia National Laboratory. This paper also presents some preliminary studies of helium cooled ITER diverter.

Paper Details

Date Published: 12 November 1993
PDF: 10 pages
Proc. SPIE 1997, High Heat Flux Engineering II, (12 November 1993); doi: 10.1117/12.163794
Show Author Affiliations
Chandrakant B. Baxi, General Atomics (United States)


Published in SPIE Proceedings Vol. 1997:
High Heat Flux Engineering II
Ali M. Khounsary, Editor(s)

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