Integrated plasma facing component calorimetry for measurement of shot integrated deposited energy in the NSTX-U

The upgrade to the National Spherical Torus eXperiment (NSTX-U) [J. Menard , Nucl. Fusion , 083015 (2012)] increases the injected neutral beam power up to 12 MW and the plasma current up to I = 2 MA for plasma durations up to 5 s. The graphite plasma facing components have been re-designed to handle...

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Bibliographic Details
Published inReview of scientific instruments Vol. 89; no. 10; p. 10J128
Main Authors Gray, T K, Allen, N, Reinke, M L, Smalley, G, Youchison, D L, Ellis, R, Jaworski, M A, Looby, T, Mardenfeld, M, Wolfe, D E
Format Journal Article
LanguageEnglish
Published United States 01.10.2018
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Summary:The upgrade to the National Spherical Torus eXperiment (NSTX-U) [J. Menard , Nucl. Fusion , 083015 (2012)] increases the injected neutral beam power up to 12 MW and the plasma current up to I = 2 MA for plasma durations up to 5 s. The graphite plasma facing components have been re-designed to handle greater heat and energy fluxes than were seen in NSTX using a castellated design. We present the experimental testing and validation of a castellated graphite target, similar to the prototype tile design, instrumented with thermocouples at various depths in the castellation. During testing, incident heat flux is provided by a programmed electron beam system and surface temperatures are measured via infrared thermography directly viewing the target surface. It was found that the thermocouple response scaled linearly with the measured surface temperature rise regardless of thermocouple depth in the castellation. A sensitivity of 14.3 °C/kJ of deposited energy was found when treating individual castellations as a semi-infinite solid.
ISSN:1089-7623
DOI:10.1063/1.5039337