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Title: Simulation of gross and net erosion of high-Z materials in the DIII-D divertor

Journal Article · · Nuclear Fusion
 [1];  [2];  [3];  [3];  [4];  [5];  [6];  [7];  [8];  [7];  [9]
  1. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
  2. General Atomics, San Diego, CA (United States); Chinese Academy of Sciences (CAS), Anhui (People's Republic of China); Oak Ridge Associated Univ., Oak Ridge, TN (United States)
  3. Univ. of Toronto, Toronto, ON (Canada)
  4. TU Wein, Vienna (Austria)
  5. Forschungszentrum Julich GmbH, Julich (Germany)
  6. General Atomics, San Diego, CA (United States); Chinese Academy of Sciences (CAS), Anhui (People's Republic of China)
  7. General Atomics, San Diego, CA (United States)
  8. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  9. Univ. of Californa San Diego, La Jolla, CA (United States)

The three-dimensional Monte Carlo code ERO has been used to simulate dedicated DIII-D experiments in which Mo and W samples with different sizes were exposed to controlled and well-diagnosed divertor plasma conditions to measure the gross and net erosion rates. Experimentally, the net erosion rate is significantly reduced due to the high local redeposition probability of eroded high-Z materials, which according to the modelling is mainly controlled by the electric field and plasma density within the Chodura sheath. Similar redeposition ratios were obtained from ERO modelling with three different sheath models for small angles between the magnetic field and the material surface, mainly because of their similar mean ionization lengths. The modelled redeposition ratios are close to the measured value. Decreasing the potential drop across the sheath can suppress both gross and net erosion because sputtering yield is decreased due to lower incident energy while the redeposition ratio is not reduced owing to the higher electron density in the Chodura sheath. Taking into account material mixing in the ERO surface model, the net erosion rate of high-Z materials is shown to be strongly dependent on the carbon impurity concentration in the background plasma; higher carbon concentration can suppress net erosion. As a result, the principal experimental results such as net erosion rate and profile and redeposition ratio are well reproduced by the ERO simulations.

Research Organization:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
Grant/Contract Number:
AC04-94AL85000; AC52-07NA27344; FC02-04ER54698; FG02-07ER54917; 2013GB107004
OSTI ID:
1238648
Alternate ID(s):
OSTI ID: 1238813
Report Number(s):
SAND-2015-10258J; 613827
Journal Information:
Nuclear Fusion, Vol. 56, Issue 1; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 43 works
Citation information provided by
Web of Science

References (32)

Analytic description of the chemical erosion of graphite by hydrogen ions journal December 1996
Tritium inventory in ITER plasma-facing materials and tritium removal procedures journal August 2008
A study of molybdenum influxes and transport in Alcator C-Mod journal May 2001
Tokamak operation with high- Z plasma facing components journal November 2005
A full tungsten divertor for ITER: Physics issues and design status journal July 2013
Fuel retention studies with the ITER-Like Wall in JET journal July 2013
Plasma Edge Cooling during rf Heating journal June 1978
Tungsten as target material in fusion devices journal June 1996
Monte Carlo simulations of tungsten redeposition at the divertor target journal January 2014
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
Modeling of sputtering erosion/redeposition—status and implications for fusion design journal July 2002
Analysis of C-MOD molybdenum divertor erosion and code/data comparison journal August 2011
Tungsten divertor erosion in all metal devices: Lessons from the ITER like wall of JET journal July 2013
Quantification of tungsten sputtering at W/C twin limiters in TEXTOR with the aid of local WF 6 injection journal December 2011
An experimental comparison of gross and net erosion of Mo in the DIII-D divertor journal July 2013
Net versus gross erosion of high- Z materials in the divertor of DIII-D journal April 2014
Measurements of net erosion and redeposition of molybdenum in DIII-D journal July 2013
Interpretive modeling of simple-as-possible-plasma discharges on DIII-D using the OEDGE code journal March 2003
Towards radiation transport modelling in divertors with the EIRENE code journal August 2002
Flux dependence of carbon erosion and implication for ITER journal March 2005
Simulation of light emission from hydrocarbon injection in TEXTOR using the ERO code journal April 2009
Estimations of erosion fluxes, material deposition and tritium retention in the divertor of ITER journal June 2009
Advanced simulation of mixed-material erosion/evolution and application to low and high-Z containing plasma facing components journal July 2013
Plasma–wall transition in an oblique magnetic field journal January 1982
Theory of the collisional presheath in an oblique magnetic field journal March 1994
Near‐surface sputtered particle transport for an oblique incidence magnetic field plasma journal August 1990
The Chodura sheath for angles of a few degrees between the magnetic field and the surface of divertor targets and limiters journal July 2012
Interpretation of divertor Langmuir probe measurements during the ELMs at JET journal August 2011
Optimization of PIC codes by improved memory management journal July 2007
Kinetic (PIC) simulations of the magnetized plasma–wall transition journal April 2005
Control of high-Z PFC erosion by local gas injection in DIII-D journal August 2015

Cited By (5)

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
Material testing facilities and programs for plasma-facing component testing journal June 2017
ERO modeling and sensitivity analysis of locally enhanced beryllium erosion by magnetically connected antennas journal December 2017
DIII-D research towards establishing the scientific basis for future fusion reactors journal June 2019

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