High-Z material erosion and its control in DIII-D carbon divertor
- Oak Ridge Associated Univ., Oak Ridge, TN (United States); Chinese Academy of Sciences (CAS), Hefei (China). Inst. of Plasma Physics; General Atomics
- Univ. of California, San Diego, CA (United States)
- Univ. of Toronto, ON (Canada). Canadian Inst. for Aerospace Studies
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- Oak Ridge Associated Univ., Oak Ridge, TN (United States)
- Forschungszentrum Julich (Germany). Inst. for Energy and Climate Research (IEK), Plasma Physics
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- General Atomics, San Diego, CA (United States)
- Univ. of Toronto, ON (Canada). Canadian Inst. for Aerospace Studies
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- 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
| 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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