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

Research Organization:
General Atomics, San Diego, CA (United States); Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES); USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
FC02-04ER54698; AC04-94AL85000; AC05-00OR22725; AC52-07NA27344
OSTI ID:
1373580
Alternate ID(s):
OSTI ID: 1406371; OSTI ID: 1530093; OSTI ID: 1890819
Report Number(s):
SAND-2017-11522J; LLNL-JRNL-839020
Journal Information:
Nuclear Fusion, Vol. 57, Issue 5; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 41 works
Citation information provided by
Web of Science

References (22)

Tungsten divertor erosion in all metal devices: Lessons from the ITER like wall of JET journal July 2013
ELM-resolved divertor erosion in the JET ITER-Like Wall journal January 2016
Plasma-wall interaction and plasma behaviour in the non-boronised all tungsten ASDEX Upgrade journal June 2009
Simulation of the plasma-wall interaction in a tokamak with the Monte Carlo code ERO-TEXTOR journal May 2000
Simulation of gross and net erosion of high- Z materials in the DIII-D divertor journal December 2015
Improved ERO modelling for spectroscopy of physically and chemically assisted eroded beryllium from the JET-ILW journal December 2016
Divertor materials evaluation system at DIII-D journal December 1992
Net versus gross erosion of high- Z materials in the divertor of DIII-D journal April 2014
Penetration depths of injected/sputtered tungsten in the plasma edge layer of TEXTOR journal July 2013
Multichord spectroscopy of the DIII‐D divertor region journal October 1992
The Filterscope journal March 2003
Recent sheath physics studies on DIII-D journal August 2015
Determination of rate coefficients for fusion-relevant atoms and molecules by modelling and measurement in the boundary layer of TEXTOR journal July 2010
Erratum: “Experimental determination of S/XB values of W I visible lines” [Phys. Plasmas 16, 122503 (2009)] journal January 2011
Tungsten spectroscopy for the measurement of W-fluxes from plasma facing components journal October 2007
Analysis of a tungsten sputtering experiment in DIII-D and code/data validation of high redeposition/reduced erosion journal May 2015
Simulation of ion beam sputtering with SDTrimSP, TRIDYN and SRIM journal August 2014
Interpretive modeling of simple-as-possible-plasma discharges on DIII-D using the OEDGE code journal March 2003
Estimations of erosion fluxes, material deposition and tritium retention in the divertor of ITER journal June 2009
Modelling of 13 CH 4 injection experiments with graphite and tungsten test limiters in TEXTOR using the coupled code ERO-SDTrimSP journal December 2007
Experimental estimation of tungsten impurity sputtering due to Type I ELMs in JET-ITER-like wall using pedestal electron cyclotron emission and target Langmuir probe measurements journal January 2016
Arcing and its role in PFC erosion and dust production in DIII-D journal July 2013

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