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Title: DiMES PMI research at DIII-D in support of ITER and beyond

Journal Article · · Fusion Engineering and Design
 [1];  [2];  [3];  [2];  [4];  [5];  [1];  [6];  [7];  [8];  [1];  [2];  [1];  [9];  [4];  [10];  [3];  [11];  [1];  [10] more »;  [2];  [10];  [1];  [8];  [2];  [6];  [8];  [2] « less
  1. Univ. of California, San Diego, La Jolla, CA (United States)
  2. General Atomics, San Diego, CA (United States)
  3. Oak Ridge Associated Univ., Oak Ridge, TN (United States)
  4. Univ. of Toronto Institute for Aerospace Studies, Toronto (Canada)
  5. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
  6. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  7. Purdue Univ., West Lafayette, IN (United States)
  8. Sandia National Lab. (SNL-CA), Livermore, CA (United States)
  9. Univ. of Tennessee, Knoxville, TN (United States)
  10. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  11. Univ. of Wisconsin, Madison, WI (United States)

An overview of recent Plasma-Material Interactions (PMI) research at the DIII-D tokamak using the Divertor Material Evaluation System (DiMES) is presented. The DiMES manipulator allows for exposure of material samples in the lower divertor of DIII-D under well-diagnosed ITER-relevant plasma conditions. Plasma parameters during the exposures are characterized by an extensive diagnostic suite including a number of spectroscopic diagnostics, Langmuir probes, IR imaging, and Divertor Thomson Scattering. Post-mortem measurements of net erosion/deposition on the samples are done by Ion Beam Analysis, and results are modelled by the ERO and REDEP/WBC codes with plasma background reproduced by OEDGE/DIVIMP modelling based on experimental inputs. This article highlights experiments studying sputtering erosion, re-deposition and migration of high-Z elements, mostly tungsten and molybdenum, as well as some alternative materials. Results are generally encouraging for use of high-Z PFCs in ITER and beyond, showing high redeposition and reduced net sputter erosion. Two methods of high-Z PFC surface erosion control, with (i) external electrical biasing and (ii) local gas injection, are also discussed. Furthermore, these techniques may find applications in the future devices.

Research Organization:
General Atomics, San Diego, CA (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC)
Grant/Contract Number:
FC02-04ER54698; AC05-00OR22725; AC52-07NA27344; AC05-06OR23100; AC04-94AL85000; DE AC05-00OR22725; FG02-07ER54917; GA-DE-SC0008698
OSTI ID:
1375007
Alternate ID(s):
OSTI ID: 1483172; OSTI ID: 1497289; OSTI ID: 1550473
Report Number(s):
LLNL-JRNL-703329; PII: S0920379617302107
Journal Information:
Fusion Engineering and Design, Vol. 124; ISSN 0920-3796
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 17 works
Citation information provided by
Web of Science

References (28)

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Cited By (3)


Figures / Tables (6)