Fuel retention measurements in Alcator C-Mod using accelerator-based in situ materials surveillance

Hartwig, Zachary S.; Barnard, Harold S.; Sorbom, Brandon N.; Lanza, Richard C.; Lipschultz, Bruce; Stahle, Peter W.; Whyte, Dennis G.

doi:10.1016/j.jnucmat.2014.09.056

Title: Fuel retention measurements in Alcator C-Mod using accelerator-based in situ materials surveillance

Journal Article · Tue Sep 30 00:00:00 EDT 2014 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2014.09.056· OSTI ID:1557816

Hartwig, Zachary S. ^[1]; Barnard, Harold S. ^[1]; Sorbom, Brandon N. ^[1]; Lanza, Richard C. ^[1]; Lipschultz, Bruce ^[2]; Stahle, Peter W. ^[1]; Whyte, Dennis G. ^[1]

Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
Univ. of York (United Kingdom)

We introduce the first in situ time- and space-resolved measurements of deuterium (D) fuel retention in plasma-facing component (PFC) surfaces using Accelerator-based In-situ Materials Surveillance (AIMS) on the Alcator C-Mod tokamak. AIMS is a novel in situ materials diagnostic technique based on the spectroscopic analysis of nuclear reaction products induced in PFC surfaces using an ~MeV beam of deuterons from a compact linear accelerator in between plasma shots. AIMS measurements of D retention on inner wall PFCs were acquired during diverted and limited plasma operations and during wall conditioning experiments. Intershot measurements demonstrate the local erosion and codeposition of boron films on PFC surfaces with a constant D/B ratio. This is steady with previous results suggesting that D codeposition with boron is insufficient to account for the net retention observed in Alcator C-Mod. Changes in deuterium concentration during boronization, electron cyclotron and glow cleanings were also measured.

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Research Organization:: Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: FG02-94ER54235; FC02-99ER54512

OSTI ID:: 1557816

Journal Information:: Journal of Nuclear Materials, Vol. 463, Issue C; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 6 works

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References (13)

Deuterium-Tritium Fuel Self-Sufficiency in Fusion Reactors Abdou, M. A.; Vold, E. L.; Gung, C. Y. Fusion Technology, Vol. 9, Issue 2 https://doi.org/10.13182/FST86-A24715	journal	March 1986
Plasma-material interactions in current tokamaks and their implications for next step fusion reactors Federici, G.; Skinner, C. H.; Brooks, J. N. Nuclear Fusion, Vol. 41, Issue 12 https://doi.org/10.1088/0029-5515/41/12/218	journal	December 2001
LIBS for tokamak plasma facing components characterisation: Perspectives on in situ tritium cartography Semerok, A.; Grisolia, C. Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, Vol. 720 https://doi.org/10.1016/j.nima.2012.12.042	journal	August 2013
Simulated plasma facing component measurements for an in situ surface diagnostic on Alcator C-Mod Hartwig, Z. S.; Whyte, D. G. Review of Scientific Instruments, Vol. 81, Issue 10 https://doi.org/10.1063/1.3478634	journal	October 2010
An in situ accelerator-based diagnostic for plasma-material interactions science on magnetic fusion devices Hartwig, Zachary S.; Barnard, Harold S.; Lanza, Richard C. Review of Scientific Instruments, Vol. 84, Issue 12 https://doi.org/10.1063/1.4832420	journal	December 2013
Hydrogenic retention with high-Z plasma facing surfaces in Alcator C-Mod Lipschultz, B.; Whyte, D. G.; Irby, J. Nuclear Fusion, Vol. 49, Issue 4 https://doi.org/10.1088/0029-5515/49/4/045009	journal	March 2009
Molybdenum erosion measurements in Alcator C-Mod Wampler, W. R.; LaBombard, B.; Lipschultz, B. Journal of Nuclear Materials, Vol. 266-269 https://doi.org/10.1016/S0022-3115(98)00663-1	journal	March 1999
Hydrogen control in Alcator C-Mod walls and plasmas Lin, Y.; Irby, J.; Lipschultz, B. Journal of Nuclear Materials, Vol. 363-365 https://doi.org/10.1016/j.jnucmat.2007.01.115	journal	June 2007
Material erosion and migration in tokamaks Pitts, R. A.; Coad, J. P.; Coster, D. P. Plasma Physics and Controlled Fusion, Vol. 47, Issue 12B https://doi.org/10.1088/0741-3335/47/12B/S22	journal	November 2005
Study and optimization of boronization in Alcator C-Mod using the Surface Science Station (S3) Ochoukov, Roman; Whyte, Dennis; Lipschultz, Bruce Fusion Engineering and Design, Vol. 87, Issue 9 https://doi.org/10.1016/j.fusengdes.2012.07.013	journal	September 2012
Operation of Alcator C-Mod with high-Z plasma facing components and implications Lipschultz, B.; Lin, Y.; Reinke, M. L. Physics of Plasmas, Vol. 13, Issue 5 https://doi.org/10.1063/1.2180767	journal	May 2006
Boronization in textor Winter, J.; Esser, H. G.; Könen, L. Journal of Nuclear Materials, Vol. 162-164 https://doi.org/10.1016/0022-3115(89)90352-8	journal	April 1989
Hydrogen absorption behavior into boron films by glow discharges in hydrogen and helium Tsuzuki, K. Journal of Nuclear Materials, Vol. 241-243, Issue 1 https://doi.org/10.1016/S0022-3115(96)00659-9	journal	February 1997

Cited By (2)

Study of the properties of thin Li films and their relationship with He plasmas using ion beam analysis in the DIONISOS experiment Bedoya, F.; Woller, K. B.; Whyte, D. G. Review of Scientific Instruments, Vol. 89, Issue 10 https://doi.org/10.1063/1.5034240	journal	October 2018
20 years of research on the Alcator C-Mod tokamaka) Greenwald, M.; Bader, A.; Baek, S. Physics of Plasmas, Vol. 21, Issue 11 https://doi.org/10.1063/1.4901920	journal	November 2014

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