13C-Tracer Experiments in DIII-D Preliminary to Thermal Oxidation Experiments to Understand Tritium Recovery in DIII-D, JET, C-Mod, and MAST

Journal Article · Mon Jun 19 04:00:00 UTC 2006 · Proceedings of the 33rd EPS Conference on Plasma Physics, vol. 30I, n/a, December 31, 2006, P5.145

OSTI ID:899425

Stangeby, P; Allen, S; Bekris, N; Brooks, N; Christie, K; Chrobak, C; Coad, J; Counsell, G; Davis, J; Elder, J; Fenstermacher, M; Groth, M; Haasz, A; Likonen, J; Lipschultz, B; McLean, A; Philipps, V; Porter, G; Rudakov, D; Shea, J ; Wampler, W; Watkins, J; West, W; Whyte, D

Retention of tritium in carbon co-deposits is a serious concern for ITER. Developing a reliable in-situ removal method of the co-deposited tritium would allow the use of carbon plasma-facing components which have proven reliable in high heat flux conditions and compatible with high performance plasmas. Thermal oxidation is a potential solution, capable of reaching even hidden locations. It is necessary to establish the least severe conditions to achieve adequate tritium recovery, minimizing damage and reconditioning time. The first step in this multi-machine project is {sup 13}C-tracer experiments in DIII-D, JET, C-Mod and MAST. In DIII-D and JET, {sup 13}CH{sub 4} has been (and in C-Mod and MAST, will be) injected toroidally symmetrically, facilitating quantification and interpretation of the results. Tiles have been removed, analyzed for {sup 13}C content and will next be evaluated in a thermal oxidation test facility in Toronto with regard to the ability of different severities of oxidation exposure to remove the different types of (known and measured) {sup 13}C co-deposit. Removal of D/T from B on Mo tiles from C-Mod will also be tested. OEDGE interpretive code analysis of the {sup 13}C deposition patterns is used to generate the understanding needed to apply findings to ITER. First results are reported here for the {sup 13}C injection experiments IN DIII-D.

• Research Organization: Lawrence Livermore National Laboratory (LLNL), Livermore, CA
• Sponsoring Organization: USDOE
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 899425
• Report Number(s): UCRL-JRNL-222266
• Journal Information: Proceedings of the 33rd EPS Conference on Plasma Physics, vol. 30I, n/a, December 31, 2006, P5.145, Journal Name: Proceedings of the 33rd EPS Conference on Plasma Physics, vol. 30I, n/a, December 31, 2006, P5.145
• Country of Publication: United States
• Language: English

Related Subjects

29 ENERGY PLANNING, POLICY, AND ECONOMY
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
CARBON
DEPOSITION
DOUBLET-3 DEVICE
HEAT FLUX
OXIDATION
PERFORMANCE
REMOVAL
RETENTION
TRITIUM
TRITIUM RECOVERY