Radiative snowflake divertor studies in DIII-D

Recent DIII-D experiments assessed the snowflake divertor (SF) configuration in a radiative regime in H-mode discharges with D 2 D 2 seeding. The SF configuration was maintained for many energy confinement times (2–3 s) in H-mode discharges ( I p =1.2 I p = 1.2  MA, P NBI =4–5 P NBI = 4 – 5  MW, and B×∇B B × ∇ B down (favorable direction toward the divertor)), and found to be compatible with high performance operation (H98y2 ⩾ 1). The two studied SF configurations, the SF-plus and the SF-minus, have a small finite distance between the primary X-point and the secondary B p B p null located in the private flux region or the common flux region, respectively. In H-mode discharges with the SF configurations (cf. H-mode discharges with the standard divertor with similar conditions) the stored energy lost per the edge localized mode (ELM) was reduced, and significant divertor heat flux reduction between and during ELMs was observed over a range of collisionalities, from lower density conditions toward a higher density H-modes with the radiative SF divertor.

[1]  T. W. Petrie,et al.  Radiative divertor experiments in DIII-D with D2 injection , 1997 .

[2]  S. Coda,et al.  Power exhaust in the snowflake divertor for L- and H-mode TCV tokamak plasmas , 2014 .

[3]  D. Ryutov,et al.  Comparison of ELM heat loads in snowflake and standard divertors , 2012 .

[4]  T. Petrie,et al.  Physics of the detached radiative divertor regime in DIII-D , 1999 .

[5]  V A Soukhanovskii,et al.  Taming the plasma–material interface with the ‘snowflake’ divertor in NSTX , 2015 .

[6]  S. Coda,et al.  Advanced divertor configurations with large flux expansion , 2013 .

[7]  S. Wolfe,et al.  A new look at density limits in tokamaks , 1988 .

[8]  D. Ryutov,et al.  A snowflake divertor: a possible solution to the power exhaust problem for tokamaks , 2012 .

[9]  S. Coda,et al.  Power distribution in the snowflake divertor in TCV , 2013 .

[10]  R. Felton,et al.  Impurity-seeded ELMy H-modes in JET, with high density and reduced heat load , 2005 .

[11]  L. Horton,et al.  ELM energy and particle losses and their extrapolation to burning plasma experiments , 2003 .

[12]  Makowski,et al.  DIII-D research towards resolving key issues for ITER and steady-state tokamaks , 2013 .

[13]  M. V. Umansky,et al.  Snowflake divertor configuration studies in National Spherical Torus Experimenta) , 2012 .

[14]  D. Ryutov Geometrical properties of a “snowflake” divertor , 2007 .

[15]  J-M Moret,et al.  "Snowflake" H mode in a tokamak plasma. , 2010, Physical review letters.

[16]  Brian Labombard,et al.  Analysis of a multi-machine database on divertor heat fluxesa) , 2011 .

[17]  T. Petrie,et al.  Compatibility of the Radiating Divertor with High Performance Plasmas in DIII-D , 2007 .