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Parameter dependencies of the experimental nitrogen concentration required for detachment on ASDEX Upgrade and JET

Journal Article · · Nuclear Materials and Energy
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  1. Culham Science Centre, Abingdon (United Kingdom)
  2. Max Planck Institute for Plasma Physics, Garching, Germany
  3. Institute for Energy and Climate Research, Juelich (Germany)
  4. Aalto Univ., Espoo (Finland)
  5. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  6. International Thermonuclear Experimental Reactor (ITER), Saint Paul Lez Durance (France)
  7. Max Planck Institute for Plasma Physics, Greifswald, Germany
  8. Univ. degli Studi di Padova (Italy)
While current tokamak experiments are beginning to use real-time feedback control systems to manage the plasma exhaust, future tokamaks still require validation of theoretical models used to predict the threshold impurity concentration required to sufficiently reduce the power and particle fluxes to the divertor. This work exploits new spectroscopic measurements of the divertor nitrogen concentration, cn, in partially detached N2-seeded H-mode plasmas on ASDEX Upgrade (AUG) and JET with the ITER-Like Wall (JET-ILW) to test the parameter dependencies of the power flowing to the outer divertor, Pdiv,outer , and the separatrix electron density, ne.sep. A least-squares regression of the AUG measurements demonstrates that the threshold cn required for detachment scales as $$c_n∝P^{1.19±0.32}_{div,outer}n^{-2.77±0.36}_{e,sep}$$. This scaling of ne,sep is also consistent with the measurements from JET which, at constant Pdiv,outer, show $$c_n∝n^{-2.43±0.27}_{e,sep}$$. The dependencies of Pdiv,outer and ne.sep is demonstrated over at least a factor of two change in both parameters and indicates a stronger dependence on ne.sep in comparison to the Lengyel model, which could be due to the assumption in this model that the heat flux channel width is independent of density. This first assessment of detachment scaling with impurity seeding highlights the need for further analysis of the systematic uncertainties of the measurement and more consistent scenarios from more tokamaks to investigate the machine size scaling.
Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Science (SC); Euratom Research and Training Programme; Engineering and Physical Sciences Research Council (EPSRC)
Grant/Contract Number:
AC05-00OR22725
OSTI ID:
1844870
Journal Information:
Nuclear Materials and Energy, Journal Name: Nuclear Materials and Energy Journal Issue: NA Vol. 28; ISSN 2352-1791
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

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