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Title: Effects of low-Z and high-Z impurities on divertor detachment and plasma confinement

Journal Article · · Nuclear Materials and Energy
 [1];  [2];  [2];  [2];  [2];  [3]
  1. Oak Ridge Associated Univ., Oak Ridge, TN (United States)
  2. General Atomics, San Diego, CA (United States)
  3. Sandia National Lab. (SNL-CA), Livermore, CA (United States)

The impurity-seeded detached divertor is essential for heat exhaust in ITER and other reactor-relevant devices. Dedicated experiments with injection of N2, Ne and Ar have been performed in DIII-D to assess the impact of the different impurities on divertor detachment and confinement. Seeding with N2, Ne and Ar all promote divertor detachment, greatly reducing heat flux near the strike point. The upstream plasma density at the onset of detachment decreases with increasing impurity-puffing flow rates. For all injected impurity species, the confinement and pedestal pressure are correlated with the impurity content and the ratio of separatrix loss power to the L-H transition threshold power. As the divertor plasma approaches detachment, the high-Z impurity seeding tends to degrade the core confinement owing to the increased core radiation. In particular, Ar injection leads to an increase in core radiation, up to 50% of the injected power, and a reduction in pedestal temperature over 60%, thus significantly degrading the confinement, i.e., with H98 reducing from 1.1 to below 0.7. As for Ne seeding, H98 near 0.8 can be maintained during the detachment phase with the pedestal temperature being reduced by about 50%. In contrast, in the N2 seeded plasmas, radiation is predominately confined in the boundary plasma, with up to 50% of heating power being radiated in the divertor region and less than 25% in the core at the onset of detachment. In the case of strong N2 gas puffing, the confinement recovers during the detachment, from ~20% reduction at the onset of the detachment to greater than that before the seeding. The core and pedestal temperatures feature a reduction of 30% from the initial attached phase and remain nearly constant during the detachment phase. The improvement in confinement appears to arise from the increase in pedestal and core density despite the temperature reduction.

Research Organization:
General Atomics, San Diego, CA (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Contributing Organization:
DIII-D Team
Grant/Contract Number:
FC02-04ER54698; AC05-06OR23100; AC04-94AL85000
OSTI ID:
1374810
Journal Information:
Nuclear Materials and Energy, Vol. 12; ISSN 2352-1791
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 16 works
Citation information provided by
Web of Science

References (11)

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Application of the radiating divertor approach to innovative tokamak divertor concepts journal August 2015
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Impurity seeding for tokamak power exhaust: from present devices via ITER to DEMO journal November 2013
High confinement/high radiated power H-mode experiments in Alcator C-Mod and consequences for International Thermonuclear Experimental Reactor (ITER) Q DT  = 10 operation journal May 2011
Effect of N2, Ne and Ar seeding on Alcator C-Mod H-mode confinement journal August 2011
Plasma surface interactions in impurity seeded plasmas journal August 2011
Impurity enrichment studies with induced scrape-off layer flow on DIII-D journal December 1998
Physics of the detached radiative divertor regime in DIII-D journal January 1999
H-mode pedestal characteristics, ELMs, and energy confinement in ITER shape discharges on DIII-D journal May 1998
ITER predictions using the GYRO verified and experimentally validated trapped gyro-Landau fluid transport model journal June 2011

Cited By (3)

Dynamics of neon ions after neon gas seeding into tokamak plasma journal September 2019
Modeling study of the onset density for divertor detachment on EAST journal October 2019
Plasma detachment in divertor tokamaks journal February 2018

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