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The inter-ELM tungsten erosion profile in DIII-D H-mode discharges and benchmarking with ERO+OEDGE modeling [The inter-ELM W erosion profile in DIII-D H-mode discharges and benchmarking with OEDGE+ERO modeling]

Journal Article · · Nuclear Fusion
 [1];  [2];  [3];  [3];  [4];  [4];  [5];  [6];  [6];  [7];  [7];  [8];  [9]
  1. General Atomics, San Diego, CA (United States); General Atomics
  2. Oak Ridge Associated Univ., Oak Ridge, TN (United States)
  3. General Atomics, San Diego, CA (United States)
  4. Univ. of California San Diego, San Diego, CA (United States)
  5. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  6. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  7. Univ. of Toronto Institute for Aerospace Studies, Toronto (Canada)
  8. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
  9. Sandia National Lab. (SNL-CA), Livermore, CA (United States)

It is important to develop a predictive capability for the tungsten source rate near the strike points during H-mode operation in ITER and beyond. H-mode deuterium plasma exposures were performed on W-coated graphite and TZM molybdenum substrates in the DIII-D divertor using DiMES. The W-I 400.9 nm spectral line was monitored by fast filtered diagnostics cross calibrated via a high-resolution spectrometer to resolve inter-ELM W erosion. The effective ionization/photon (S/XB) was calibrated using a unique method developed on DIII-D based on surface analysis. Inferred S/XB values agree with an existing empirical scaling at low electron density (ne) but diverge at higher densities, consistent with recent ADAS atomic physics modeling results. Edge modeling of the inter-ELM phase is conducted via OEDGE utilizing the new capability for charge-state resolved carbon impurity fluxes. ERO modeling is performed with the calculated main ion and impurity plasma background from OEDGE. ERO results demonstrate the importance a mixed-material surface model in the interpretation of W sourcing measurements. As a result, it is demonstrated that measured inter-ELM W erosion rates can be well explained by C→W sputtering only if a realistic mixed material model is incorporated.

Research Organization:
General Atomics, San Diego, CA (United States)
Sponsoring Organization:
USDOE
Grant/Contract Number:
FC02-04ER54698
OSTI ID:
1373580
Alternate ID(s):
OSTI ID: 1406371
OSTI ID: 1530093
OSTI ID: 1890819
OSTI ID: 22925711
Journal Information:
Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 5 Vol. 57; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English

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Cited By (13)

Dynamic divertor control using resonant mixed toroidal harmonic magnetic fields during ELM suppression in DIII-D journal May 2018
Effects of carbon impurities on the power radiation and tungsten target erosion in EAST journal July 2018
Impact of ELM control techniques on tungsten sputtering in the DIII-D divertor and extrapolations to ITER journal June 2019
Simulations on W impurity transport in the edge of EAST H-mode plasmas journal October 2018
Advances in neutral tungsten ultraviolet spectroscopy for the potential benefit to gross erosion diagnosis journal August 2019
Effect of carbon and tungsten plasma-facing materials on the divertor and pedestal plasma in EAST journal October 2019
Reduced model of high-Z impurity redeposition and erosion in tokamak divertor and its application to DIII-D experiments journal November 2019
Tungsten erosion by unipolar arcing in DIII-D journal October 2017
Measurement and modeling of aluminum sputtering and ionization in the DIII-D divertor including magnetic pre-sheath effects journal August 2018
Erosion, screening, and migration of tungsten in the JET divertor journal August 2019
Modeling of inter- and intra-edge-localized mode tungsten erosion during DIII-D H-mode discharges journal October 2019
ERO modeling and analysis of tungsten erosion and migration from a toroidally symmetric source in the DIII-D divertor journal November 2019
Advances in neutral tungsten ultraviolet spectroscopy for the potential benefit to gross erosion diagnosis text January 2019

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Journal Article · Fri Oct 04 00:00:00 EDT 2019 · Nuclear Fusion · OSTI ID:1577445