In Part I it was shown that values of T eu and n eu in the SOL of single null, high recycling divertor discharges in JET and Alcator C-Mod are related approximately as T eu ∝ n 1/2 eu , where (T eu , n eu ) are the values of plasma temperature and density on any given flux tube at the `upstream' end, for example, halfway between the two targets. This implies that the upstream radial decay length can be expected to approximately satisfy λ n /λ T ≈ 1/2, in the conduction limited regime. Other simple correlations, such as between target ion saturation current density, J sat,t , and n eu are also implied, and are found to hold for the database considered. The variation of n eu with ⟨n e ⟩ is established for the JET database and this is used to express the region in (⟨n e ⟩, P SOL ) space for conduction limited operation, i.e. the respective transitions to sheath limited and detached divertor regimes.
No takes yet. Share an insight, caveat, or question.
Erents et al. (2000) studied this question.
Synapse has enriched 5 closely related papers on similar clinical questions. Consider them for comparative context: