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

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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} ... continued below

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Stangeby, P; Allen, S; Bekris, N; Brooks, N; Christie, K; Chrobak, C et al. June 19, 2006.

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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.

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PDF-file: 6 pages; size: 0.6 Mbytes

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  • Journal Name: Proceedings of the 33rd EPS Conference on Plasma Physics, vol. 30I, n/a, December 31, 2006, P5.145

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  • Report No.: UCRL-JRNL-222266
  • Grant Number: W-7405-ENG-48
  • Office of Scientific & Technical Information Report Number: 899425
  • Archival Resource Key: ark:/67531/metadc887983

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  • June 19, 2006

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  • Sept. 22, 2016, 2:13 a.m.

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  • Dec. 2, 2016, 6:50 p.m.

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Stangeby, P; Allen, S; Bekris, N; Brooks, N; Christie, K; Chrobak, C et al. 13C-Tracer Experiments in DIII-D Preliminary to Thermal Oxidation Experiments to Understand Tritium Recovery in DIII-D, JET, C-Mod, and MAST, article, June 19, 2006; Livermore, California. (digital.library.unt.edu/ark:/67531/metadc887983/: accessed September 19, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.