FY2009 NSTX Research Forum
8 - 10 December, 2008
The
National Spherical Torus Experiment (NSTX) Research Forum
for 2009 is scheduled for December 8 - 10, 2008, at the
Princeton Plasma Physics Laboratory in Princeton, NJ USA.
Team members and prospective collaborators are invited to
attend or participate remotely.
The
Research Forum is intended to provide team members the
opportunity to present ideas for experiments to be
conducted on NSTX in the forthcoming run. Both
well-developed and new ideas in the early stages of
development are welcomed. For the 2009 experiments
Proposals for experiments to be performed in 2009 can be
submitted for discussion at the Research Forum through
this website.
There
are no registration fees for the meeting, but
researchers from other institutions must pre-register to
participate. Intending participants from other
institutions who are US citizens should send their names
and affiliations to Joanne Savino (JSavino@pppl.gov)
to register; non-US citizens will need to submit a
PPPL Foreign Visitor
form in advance of the meeting. Please email Joanne
Savino (JSavino@pppl.gov)
as soon as possible.
High Priority Experimental Goals for 2009 (see each area for all priorities; all ideas are welcome)
- Assess hydrogenic species retention, and characterize pumping of hydrogenic species by lithium coated plasma facing components (FY09 Joule milestone)
- Determine the relationship of ELM properties to discharge boundary shape, lithium conditioning, and 3D resonant magnetic perturbations (RMPs), and compare stability of pedestal/ELMs with model calculations (R10-3)
- Assess active and passive RWM stabilization physics for improved mode control (R09-1)
- Develop an understanding of the deleterious effects of disruptions in an ST, including halo current generation and the properties of the thermal quench
- Investigate the mechanisms governing electron transport
- L-H transition physics
- Study possible plasma current density profile modification by super-Alfvenic ion driven modes (R09-2)
- Characterize and optimize HHFW coupling in Deuterium H-Mode plasmas using the new double-feed antenna configuration and lithium edge density control
Solenoid-Free Startup and Rampup
- Improve coupling of inductive ramp-up to CHI plasmas
- Increase ohmic flux savings using CHI
Advanced Scenarios and Control
- Characterize non-inductive current drive fraction versus elongation, proximity to beta limit, and plasma density (R09-3)
- Attempt to achieve long-pulse density control for increased neutral beam current drive fraction using improved fueling and lithium conditioning