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

Journal Article · · Review of Scientific Instruments
DOI:https://doi.org/10.1063/1.5039337· OSTI ID:1483183

Here, the upgrade to the National Spherical Torus eXperiment (NSTX-U) increases the injected neutral beam power up to 12 MW and the plasma current up to Ip = 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.

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Science (SC)
Grant/Contract Number:
AC05-00OR22725; AC02-09CH11466; AC52-07NA27344
OSTI ID:
1483183
Alternate ID(s):
OSTI ID: 1479834
Journal Information:
Review of Scientific Instruments, Vol. 89, Issue 10; ISSN 0034-6748
Publisher:
American Institute of Physics (AIP)Copyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 5 works
Citation information provided by
Web of Science

References (10)

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Heat flux measurement techniques
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Development and Performance of Tungsten-Coated Graphitic Foam for Plasma-Facing Components journal May 2019

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