Helium-cooled divertor module for fusion devices

Chandrakant B. Baxi

doi:10.1117/12.163794

12 November 1993 Helium-cooled divertor module for fusion devices

Chandrakant B. Baxi

Proceedings Volume 1997, High Heat Flux Engineering II; (1993) https://doi.org/10.1117/12.163794
Event: SPIE's 1993 International Symposium on Optics, Imaging, and Instrumentation, 1993, San Diego, CA, United States

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.

Citation Download Citation

Chandrakant B. Baxi "Helium-cooled divertor module for fusion devices", Proc. SPIE 1997, High Heat Flux Engineering II, (12 November 1993); https://doi.org/10.1117/12.163794

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