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Title: High-Z material erosion and its control in DIII-D carbon divertor

Journal Article · · Nuclear Materials and Energy
 [1];  [2];  [3];  [4];  [5];  [6];  [7];  [2];  [8];  [8];  [9];  [8];  [5];  [6];  [10];  [8];  [10];  [10];  [8];  [8] more »;  [11];  [7];  [5];  [4] « less
  1. Oak Ridge Associated Univ., Oak Ridge, TN (United States); Chinese Academy of Sciences (CAS), Hefei (China). Inst. of Plasma Physics; General Atomics
  2. Univ. of California, San Diego, CA (United States)
  3. Univ. of Toronto, ON (Canada). Canadian Inst. for Aerospace Studies
  4. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
  5. Oak Ridge Associated Univ., Oak Ridge, TN (United States)
  6. Forschungszentrum Julich (Germany). Inst. for Energy and Climate Research (IEK), Plasma Physics
  7. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  8. General Atomics, San Diego, CA (United States)
  9. Univ. of Toronto, ON (Canada). Canadian Inst. for Aerospace Studies
  10. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  11. Technische Univ. Wien, Vienna (Austria). Fusion@OAW, Inst. of Applied Physics; Univ. of Innsbruck (Austria). Inst. for Theoretical Physics

It is expected that high-Z materials will be used as plasma-facing components (PFCs) in future fusion devices, making the erosion of high-Z material a key issue for high-power, long pulse operation. High-Z material erosion and redeposition have been studied using tungsten and molybdenum coated samples exposed in well-diagnosed DIII-D divertor plasma discharges. By coupling dedicated experiments and modelling using the 3D Monte Carlo code ERO, the roles of sheath potential and background carbon impurities in determining high-Z material erosion are identified. Different methods suggested by modelling have been investigated to control high-Z material erosion in DIII-D experiments. The erosion of Mo and W are found to be strongly suppressed by local injection of methane and deuterium gases. The 13C deposition resulting from local 13CH4 injection also provides information on radial transport due to E×B drifts and cross field diffusion. Finally, D2 gas puffing is found to cause 2 local plasma perturbation, suppressing W erosion because of the lower effective sputtering yield of W at lower plasma temperature and for higher carbon concentration in the mixed surface layer.

Research Organization:
General Atomics, San Diego, CA (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE); USDOE National Nuclear Security Administration (NNSA); USDOE Office of Science (SC), Fusion Energy Sciences (FES) (SC-24); National Magnetic Confinement Fusion Science Program of China; National Natural Science Foundation of China
Grant/Contract Number:
FC02-04ER54698; SC0008698; AC05-06OR23100; FG02-07ER54917; AC05-00OR22725; AC04-94AL85000
OSTI ID:
1374815
Journal Information:
Nuclear Materials and Energy, Journal Name: Nuclear Materials and Energy Vol. 12; ISSN 2352-1791
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (20)

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Analysis of a tungsten sputtering experiment in DIII-D and code/data validation of high redeposition/reduced erosion journal May 2015
Plasma-wall interaction and plasma behaviour in the non-boronised all tungsten ASDEX Upgrade journal June 2009
Deposition and re-erosion studies by means of local impurity injection in TEXTOR journal August 2011
Interpretation of divertor Langmuir probe measurements during the ELMs at JET journal August 2011
Tungsten divertor erosion in all metal devices: Lessons from the ITER like wall of JET journal July 2013
A full tungsten divertor for ITER: Physics issues and design status journal July 2013
An experimental comparison of gross and net erosion of Mo in the DIII-D divertor journal July 2013
Measurements of net erosion and redeposition of molybdenum in DIII-D journal July 2013
Control of high-Z PFC erosion by local gas injection in DIII-D journal August 2015
Plasma-surface interaction in the Be/W environment: Conclusions drawn from the JET-ILW for ITER journal August 2015
Near‐surface sputtered particle transport for an oblique incidence magnetic field plasma journal August 1990
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The Chodura sheath for angles of a few degrees between the magnetic field and the surface of divertor targets and limiters journal July 2012
Simulation of gross and net erosion of high- Z materials in the DIII-D divertor journal December 2015
Net versus gross erosion of high- Z materials in the divertor of DIII-D journal April 2014
Simulation of light emission from hydrocarbon injection in TEXTOR using the ERO code journal April 2009

Cited By (1)

Reduced model of high-Z impurity redeposition and erosion in tokamak divertor and its application to DIII-D experiments journal November 2019

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