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High heat-flux response of high-conductivity graphitic foam monoblocks

Conference · · Fusion Engineering and Design
 [1];  [2];  [1];  [1];  [3];  [3]
  1. ORNL
  2. Missouri University of Science and Technology
  3. Max Planck Institute for Plasma Physics, Garching, Germany
+ Show Author Affiliations
Plasma-facing components based on the so-called monoblock design are planned for use in the divertor region of long-pulse plasma devices such as ITER and JT-60SA due to their capacity to handle high heat fluxes with active water cooling. The plasma-facing materials that are preferred for these monoblocks are tungsten for ITER or carbon-carbon fiber reinforced carbon (CFC) for JT-60SA. The requirements for the plasma-facing components include the ability to handle high plasma fluxes resulting in high temperatures. Therefore, reasonably high thermal conductivity is required. In this study, high thermal conductivity graphite foam is explored as a monoblock material. Four different test articles are created, two with the foam brazed to CuCrZr tubes, and two with the foam press fit to the tubes. These monoblocks are then thermally cycled at 8 MW/m2 in the high heat-flux test facility GLADIS to examine their robustness for long-pulse divertor applications. Experimental results are compared with computational fluid dynamics simulation. Graphite foam shows promise for use in a plasma-facing component, but further development is necessary to address the significant drop in thermal conductivity at high temperatures.
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Science (SC)
DOE Contract Number:
AC05-00OR22725
OSTI ID:
1559724
Conference Information:
Journal Name: Fusion Engineering and Design Journal Volume: 146
Country of Publication:
United States
Language:
English

References (8)

Infrared thermography inspection for monoblock divertor target in JT-60SA journal October 2014
High heat flux facility GLADIS: journal August 2007
The role of structure on the thermal properties of graphitic foams journal June 2004
Design and Test of Wendelstein 7-X Water-Cooled Divertor Scraper journal May 2018
Overview of Design and Analysis Activities for the W7-X Scraper Element journal September 2016
High heat flux components—Readiness to proceed from near term fusion systems to power plants journal January 2010
Thermal-hydraulics modeling for prototype testing of the W7-X high heat flux scraper element journal October 2017
ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces journal January 2005

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