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Student
Abstracts: Physics at PPPL
Effect of Nearby Conducting Structure on the Macroscopic
Stability of NSTX Plasmas. ANNIE AHNERT (The University of Arizona, Tucson,
AZ 85721) DR. JON MENARD (Princeton Plasma Physics Laboratory, Princeton, NJ
08543) .
The ability to predict the macroscopic stability of plasma is an important part
of current magnetic fusion research. There are many different programs to
predict the stability of plasma, but these programs also require
approximations, such as idealized shapes for the closest conducting surface
adjacent to the plasma. A program that was able to generate the approximate
shape of the conducting surface was written with parameters to control the
smoothness of the approximation. The program was used to generate conducting
wall shapes accurately simulating the effects of the National Spherical Torus
Experiment (NSTX) vacuum vessel and passive plates on the n=1 kink mode
stability of a high beta=40% NSTX target plasma. Future studies will
investigate the effect of the inner and outer conducting wall on lower beta
plasmas.
BPST Coil Design and Optimization. ERIC HARKLEROAD
(Princeton University, Princeton, NJ 08544) NEIL POMPHREY (Princeton Plasma
Physics Laboratory, Princeton, NJ 08543) .
We seek an optimal configuration of Ohmic Heating (OH) and Equilibrium Field (EF)
coils for the proposed Burning Plasma Spherical Tokamak (BPST) at PPPL. To
determine the EF coil positions for the new device, we scale the design of the
National Spherical Torus eXperiment (NSTX), and determine a discrete set of
candidate coil positions. We then employ the Tokamak Simulation Code (TSC) to
isolate which small subset of these coils experience the greatest changes in
current as plasma shape and current profile vary. We select these as our
design. Upon fixing the EF coil positions, we optimize the height of the center
stack by varying the height and noting variations in the ohmic field error,
selecting a height at which these errors are acceptably small. We next seek an
ohmic current distribution-a set of EF and OH coil currents which produces
little or no field within the plasma. The field produced by an arbitrary
current distribution is invariant under addition of a scalar multiple of an
ohmic distribution. We outline two methods of approximating an ohmic
distribution and implement them in Fortran 90, calling on subroutine E04UNF
from the Numerical Algorithms Group (NAG) Library, a specialized routine
designed to minimize a function of many variables. We also include provisions
for efficient optimization of a center stack of ohmic heating coils. Coupled
with other studies and simulation codes, our coil design and optimization codes
have the potential to make significant contributions to the design of BPST.
Development and Analysis of an Electrically Tunable
Optical Filter. KRISTI HULTMAN (Harvey Mudd College, CLaremont, CA 91711)
FRED LEVINTON (Princeton Plasma Physics Laboratory, Princeton, NJ 08543) .
The focus of my research experience was the development of an electrically
tunable optical filter using a He-Ne laser and a combination of polarizers (P),
LN crystals (C), and retarders (R). A variable high voltage power supply was
attached to the LN crystals, allowing us to optimize transmission of specific
wavelengths. The retarder used was made from 3 polarizing lenses, with the
middle lens rotated 59.0° off axis. For analysis of the filter transmission, a
LabView program was written to display the image of the beam captured using a
CCD camera, as well as peak and average intensities, and save the data. We were
successful in tuning the laser to a minimum and maximum in both the PCP and
PCRCP configurations, and can resolve wavelength variations of less than 0.1nm.
A stable, easily tunable optical filter would allow for a cleaner signal when
looking at a specific wavelength or allow you to block out a certain
wavelength, thus the noise from unwanted wavelengths would be reduced.
Electron Bernstein Wave Polarization Measurements on
CDX-U. THOMAS KRAMER (Brown University, Providence, RI 02912) PHILIP
EFTHIMION (Princeton Plasma Physics Laboratory, Princeton, NJ 08543) .
Mode-converted (MC) EBWs offer an attractive path for electron temperature
measurement, heating, and current drive in overdense plasmas (Plasma frequency
>> Cyclotron frequency). A quad-ridged antenna was installed in CDX-U
with a movable limiter, which shortens electron density scale length at the MC
layer and hence optimises MC efficiency. Electrostatic EBWs are expected to MC
to X-mode electromagnetic waves. Measurements were made with both the X- and
O-mode aligned antennas, and the X/O ratio was calculated. An X/O ratio > 2
was observed with the antenna near the MC layer, in contrast to a ratio of 1.2
measured previously with an antenna outside the vessel. A ratio of ~1 was seen
with the antenna far from the MC layer, possibly due to reflections between the
plasma and vessel wall causing polarization scrambling. Reduction of the X/O
ratio was observed when the limiter was extended, likely due to polarization
mixing caused by reflection or refraction at the limiter surface in front of
the antenna. *Work Supported by U.S. DOE Contract DE-AC02-76CH03073
TSC Plasma Simulations for NSTX Center Stack Upgrade.
ANDREW OSGOOD (Muhlenberg College, Allentown, PA 18104) DR. STANLEY KAYE
(Princeton Plasma Physics Laboratory, Princeton, NJ 08543) .
The National Spherical Torus Experiment, or NSTX, is the primary fusion device
at PPPL. In an effort to continue efficient use of the machine, a planned
center stack upgrade needs numerous computer simulations to determine its
practicality. Using specially designed programs called Tokamak Simulation Code,
or TSC, numerous qualities and quantities can be accurately simulated.
Initially, a shape range had to be determined using the static version of TSC,
since the shape of the plasma is integral in many other practical aspects such
as stability. Once a stable static shape range was determined, the pf coil
currents could be used in the dynamic TSC version to develop a more plausible
plasma that evolved through time. For both 1.5MA and 3.0MA plasmas (the only two
plasma currents simulated) the TSC produced acceptably wide shape ranges. The
1.5MA plasmas found a wider range, since much higher values of li and a lower
current allowed control from pf coils through lower currents. (The pf coils
have maximum current limits that restrained most 3.0MA runs.) These runs
produced values that were used as input for the dynamic TSC runs, but also
illustrated that an adequate shape range could be produced using the new center
stack upgrade parameters. The coil currents produced in static simulations will
be used in continuing dynamic simulations that strive for specific plasma
properties according to future needs. Starting the dynamic runs has shown that
this is possible and can produce viable results, and many more simulations will
follow.
Study of Magnetic Damping in Liquid Metal Surface Waves.
DAVID PACE (University of the Pacific, Stockton, CA 95211) DR. HANTAO JI
(Princeton Plasma Physics Laboratory, Princeton, NJ 08543) .
Knowledge of liquid metal surface waves and instabilities provides insight
regarding turbulence in plasmas and the magnetohydrodynamic (MHD) model used to
describe plasmas generally. Such work is also critical in the development of
liquid lithium walls to be used in fusion reactors. The Liquid Metal Experiment
(LMX) is designed to study magnetically induced damping of liquid gallium
surface waves by driving such waves in the presence of a magnetic field.
Previous work measured the dispersion relation and confirmed that a magnetic
field aligned perpendicularly to the direction of wave propagation has no
effect. More recent findings have demonstrated that a magnetic field aligned
parallel to the direction of wave propagation causes significant damping of the
waves which follows a gaussian dependence, and confirmed that the wave number
varies in the presence of a magnetic field.
Stability Tests of Hydrodynamic Flows in Water for
Laboratory Study of Magnetorotational Instability. ETHAN SHOSHAN (Rutgers
University, New Brunswick, NJ 07751) HANTAO JI (Princeton Plasma Physics
Laboratory, Princeton, NJ 08543) .
Magnetorotational Instability (MRI) is a powerful candidate mechanism for the
fast transport of angular momentum in magnetized accretion disks. In an
accretion disk, when the mass spirals in towards the stellar object, due to
gravity, the velocity increases to conserve angular momentum. When the force of
gravity is balanced with the centripetal force, the viscosity pulls it in
towards the central compact object, which is too small to explain the fast
transport of mass, so there must be another reason. Hydrodynamic (HD)
instabilities, like the Rayleigh instability, are ineffective in producing
turbulence in accretion disks because it requires a negative gradient of
specific angular momentum. Magnetohydrodynamics provides a better description
of plasma in hot accretion flows where angular momentum has an extra degree of
freedom due to the presence of the magnetic field. The radial transport of
angular momentum due to MRI will hopefully explain how mass gets accreted onto
a stellar object. Despite the popularity of MRI, it has never been tested in
the laboratory. In an attempt to demonstrate MRI in the laboratory, a
magnetized couette flow experiment using gallium is proposed. Before gallium is
used, a prototype experiment using water has been constructed to study linear
and nonlinear HD instability in the (omega1, omega2) space. HD stability can be
monitored using particle imaging velocimeter techniques, which will serve as a
reference for effects due to the MRI mechanism.
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