Ion drifts in a snowflake divertor

"Snowflake" divertor configuration in NSTX

Taming the Plasma Material Interface with the "Snowflake" Divertor in NSTX

Steady-state handling of divertor heat flux is a critical issue for ITER and future conventional and spherical tokamaks with compact high power density divertors. A novel ”snowflake” divertor (SFD) configuration was theoretically predicted to have significant magnetic geometry benefits for divertor heat flux mitigation, such as an increased plasma-wetted area and a higher divertor volume availa...

IC/P4-8 A Snowflake Divertor: a Possible Way of Improving the Power Handling in Future Fusion Facilities

Handling high power loads on plasma facing components is one of the critical issues in developing an economically competitive fusion reactor or fusion test facilities based on a tokamak. In this study, we provide a detailed analysis of a relatively unexplored approach to this problem based on the use of divertors with the poloidal magnetic field structure closely approaching a second-order null...

Spectroscopic Measurements of Hydrogen Ion Temperature During Divertor Recombination

{ Chord covers range of n e , T i , { Other processes do contribute, {) need to simulate spectrum to validate interpretation. Here: demonstrate using DEGAS 2 with UEDGE C-Mod plasma.

EX/P4-21 The Effect of Magnetic Balance and Particle Drifts on Radiating Divertor Behavior in DIII-D

Success of the puff-and-pump radiating divertor approach depends sensitively on both the divertor magnetic geometry and the ion B B drift direction. In the puff-and-pump scenario used in this study, argon impurities were injected into the private flux region, while plasma flows into both the inner and outer divertors were enhanced by a combination of particle pumping near both divertor targets ...