Modeling detachment physics in the NSTX 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...

Understanding divertor detachment through CRETIN modeling — a work in progress

Integrated models to study the impact of ELMs and disruptions on lithium in the NSTX divertor

Lithium as a potential plasma-facing material has many attractive features including a reduction in recycling of hydrogenic species and ability to withstand high heat and neutron fluxes in fusion reactors. Recent analysis of the National Spherical Torus eXperiment (NSTX) device has shown significant and recurring benefits of lithium coatings on plasma-facing components performance. To self-cons...

Divertor design for the tokamak physics experiment

In this paper we discuss the divertor design for the planned TPX tokamak, which will explore the physics and technology of steady state (1000 s pulses) heat and particle removal in high confinement (up to 4 × L-mode), high beta (up to /3 N = 5) divertor plasmas sustained by non-inductive current drive. TPX will operate in the double-null divertor configuration, with actively cooled graphite tar...