skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Thermo-Oxidation of Tokamak Carbon Dust

Conference ·
OSTI ID:927636

The oxidation of dust and flakes collected from the DIII-D tokamak, and various commercial dust specimens, has been measured at 350 ºC and 2.0 kPa O2 pressure. Following an initial small mass loss, most of the commercial dust specimens showed very little effect due to O2 exposure. Similarly, dust collected from underneath DIII-D tiles, which is thought to comprise largely Grafoil™ particulates, also showed little susceptibility to oxidation at this temperature. However, oxidation of the dust collected from tile surfaces has led to ~ 18% mass loss after 8 hours; thereafter, little change in mass was observed. This suggests that the surface dust includes some components of different composition and/or structure – possibly fragments of codeposited layers. The oxidation of codeposit flakes scraped form DIII-D upper divertor tiles showed an initial 25% loss in mass due to heating in vacuum, and the gradual loss of 30-38% mass during the subsequent 24 hours exposure to O2. This behavior is significantly different from that observed for the oxidation of thinner DIII-D codeposit specimens which were still adhered to tile surfaces, and this is thought to be related to the low deuterium content (D/C ~ 0.03 – 0.04) of the flakes.

Research Organization:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
DOE - SC
DOE Contract Number:
DE-AC07-99ID-13727
OSTI ID:
927636
Report Number(s):
INL/CON-08-13664; TRN: US0804806
Resource Relation:
Conference: 13th International Conference on Fusion Reactor Materials,Nice, France,12/10/2007,12/14/2007
Country of Publication:
United States
Language:
English

Similar Records

Operation of DIII-D with all-graphite walls
Journal Article · Fri Jul 01 00:00:00 EDT 1994 · Journal of Vacuum Science and Technology, A (Vacuum, Surfaces and Films); (United States) · OSTI ID:927636

The effect of thermo-oxidation on plasma performance and in-vessel components in DIII-D
Journal Article · Tue Jan 01 00:00:00 EST 2013 · Nuclear Fusion · OSTI ID:927636

Dust Studies in DIII-D and TEXTOR
Conference · Tue Feb 17 00:00:00 EST 2009 · OSTI ID:927636