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New Additions
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Lasers converge on a fusion target at the University of Rochester's OMEGA facility (Courtesy University of Rochester).
BETTER TABLETOP ACCELERATORS FUSION
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A couple of caveats: laser accelerators produce particles over a spectrum of energies, and only a few particles are at the highest energies. But even the lower-energy particles are useful for applications, Umstadter says, and there are enough of them within a narrow energy range to extract a monochromatic beam. In fact, researchers are now considering using the tabletop accelerator as an injector for coherent x-ray sources, such as the LCLS (Linac Coherent Light Source) facility proposed at the Stanford Linear Accelerator Center (SLAC). The natural shortness of the tabletop pulses makes it potentially possible to eliminate the usual requirement for magnetic beam compression, in which an elaborate series of magnets causes the charged particles of a conventional injector to travel different distances so that they pile up in time. Preliminary experiments (from three different countries) indicate that when ultrashort light pulses (less than 40 quadrillionths of a second) are used, the electrons might be accelerated by a novel mechanism, in which the laser light directly accelerates the electrons rather than indirectly through oscillations of the plasma. Previous experiments were done with laser pulses that lasted greater than 400 quadrillionths of a second, or approximately ten times longer. Umstadter will review the year's many advances in this emerging discipline, which has been termed "high-field science." (Paper LR1.001) |
An electron beam created by a tabletop laser
2. Improvements in "Direct Drive" Fusion
Plasma researchers have made the first use of a technique for improving
a major form of laser-induced nuclear fusion known as "direct drive."
In direct-drive fusion, lasers from many directions deposit energy
directly on a shell containing fusion fuel; the light causes the shell
to implode and trigger fusion reactions. Traditionally, direct drive
has suffered from serious limitations, mainly because non-uniformities
in the laser light's intensity cause the shells to implode in a less
than optimal fashion. At the University of Rochester's 60-beam OMEGA
laser system, researchers (David D. Meyerhofer, 716-275-0255,
ddm@lle.rochester.edu) have
utilized a method, known as "polarization smoothing," for significantly
improving the laser beam uniformity. In a large laser such as the ones
at OMEGA, each beam typically has unavoidable spatial fluctuations in
intensity. To reduce these intensity fluctuations, researchers split
each beam into two parts, each containing complementary or "orthogonal"
components of the beam's electric field. Each of the polarized beams
fluctuates independently of the other, so overlapping them averages or
smooths out such intensity modulations. When such beams were used to
induce fusion reactions (with the fuel shell imploding to about 7% of
its original radius or 1/3000 of its original volume) the primary
neutron yield from deuterium or deuterium-tritium filled plastic shells
increased by about 70% compared to similar implosions without
polarization smoothing. The emission of neutrons is generally
proportional to the fusion reaction rate. At the same time, the
smoother beams increased the compressed shell's "areal density"
(density times radius) by 40-70%. Maximizing the areal density is a
major factor for eventually achieving self-sustaining fusion reactions
with laser fusion because it increases the opportunity for alpha
particles, created as a result of fusion reactions inside the shell,
to deposit their energy and heat the plasma further. Theoretical models
predict additional improvements. These results bode well for
direct-drive implosions of targets on OMEGA and Livermore's planned
National Ignition Facility. This work will be described in papers
BI3.003, HO2.001-004 and H01.007-008.
A laser fusion shot going off in the OMEGA target chamber.
3. Discovery of Radio Wave Trigger Doubles Plasma Density in Fusion
Device
Researchers have discovered a powerful tool for creating
and manipulating coveted "internal transport barriers" which prevent
unwanted heat leakage from magnetically confined fusion plasmas. At
the Alcator C-Mod National Tokamak Facility, located at the MIT Plasma
Science and Fusion Center, researchers are developing a technique known
as "off-axis ion cyclotron radio frequency" (ICRF) heating. C-Mod is a
tokamak, a doughnut-shaped device which uses magnetic fields to confine
plasmas. Normally, ions in these plasmas circle around the magnetic
fields at different rates; the ions' resulting "cyclotron frequencies"
vary according to their positions with respect to the tokamak's many
fields. And for reasons not completely understood, the overall plasma
rotates around the tokamak. In traditional techniques for heating the
plasma with radio waves, researchers send in waves with a frequency that
matches the cyclotron frequency of ions at the center of the plasma.
However, MIT researchers studied the effects of moving the resonance
location for the ICRF heating; in other words, they applied a radio
frequency that matched the cyclotron frequency of ions at a location
elsewhere in the plasma. When this resonance location was moved
sufficiently far away from the center of the plasma, the overall rotation
of the plasma was significantly slowed, or even reversed, and
simultaneously with this change, a clear internal transport barrier
developed, resulting in an extraordinary peaking of the plasma density,
one that was at least two times greater than before. Internal transport
barriers have been created before, but they often require the introduction
of neutral atom beams which could not be feasibly placed in the designs
envisioned for commercial fusion reactors. This new approach of creating
internal barriers could prove to be extremely important, as it is
potentially attractive for reactor applications.
Paper HI2.001 - contact Catherine Fiore, 617-253-8440
fiores@psfc.mit.edu; John Rice,
617-253-5395 rice@psfc.mit.edu
A plasma created at the Alcator C-MOD facility.
4. Microwave Surgery on Fusion Plasmas
Recent experiments in Germany and the United States have shown that fusion reaction
rates and other properties in magnetically confined plasmas can be significantly improved
by a relatively small amount of microwave power, applied at precisely the right location
in the plasma. Tokamak plasmas and indeed most magnetically trapped plasmas are
subject to the growth of "magnetic islands." These islands break up the smooth magnetic
field surfaces that confine the plasma, leading to more rapid loss of heat from the plasma
and making it more difficult to reach the high temperatures and pressures needed for
nuclear fusion. Experiments first carried out in the ASDEX Upgrade tokamak (Max-
Planck Institute, Garching, Germany) and, more recently, in the DIII-D tokamak (General
Atomics, San Diego, CA) have confirmed theoretical predictions that islands due to high
plasma pressure can be eliminated by adding a small amount of added electrical current at
the island location. A narrow beam of microwaves can drive the desired current, with
surgical precision, by interacting with electrons at the appropriate location. In
experiments to be reported at the meeting, a magnetic island degraded the plasma
pressure by about 20%. Adding one megawatt of microwave power, about one-tenth of
the total power needed to heat the plasma, drove enough current to suppress the island.
This allowed the plasma pressure to recover, resulting in a 35% increase in the fusion
reaction rate at DIII-D. These pioneering experiments show the feasibility of improving
the performance of fusion plasmas by small, precisely controlled modifications of their
internal structure. Similar experiments have been carried out in tokamaks in the UK and
Japan.
Paper GI1.001 - Hartmut Zohm
Max Planck Institut fur Plasmaphysik
011-49-89-3299-1925
haz@ipp.mpg.de
Robert La Haye
General Atomics
(858) 455-3134
lahaye@fusion.gat.com
Temperature measurements show an island structure in a magnetically confined plasma
(left, center of figure). After microwave "surgery" (right) the island has been eliminated. (ASDEX
Upgrade tokamak, Germany). A temperature of 1000 electron volts is 11 million degrees centigrade.
5. Fusion in a Beer Can?
Researchers are investigating an approach that offers the possibility of creating fusion
energy in a small, inexpensive device. Known as Magnetized Target Fusion (MTF), the
approach can potentially be developed on a short time scale because of its low cost. The
MTF technique preheats and injects magnetized fusion fuel into an aluminum cylinder
the size of a large beer can. Then the "beer can" is rapidly compressed by driving a giant
electrical current along the wall of the cylinder. The compressed high-density plasma
fuel burns in a few millionths of a second. The fast-moving solid metal wall, which
compresses the fuel, has been developed for defense programs. The fuel-compression
region implodes at pressures millions of times greater than that of the Earth's atmosphere.
The process is analogous to that of a diesel engine, which compresses fuel to conditions
where it more readily burns. The essential advantage of MTF is its potential to be tested
for scientific feasibility and even developed up to the prototype stage using apparatus that
costs a fraction of conventional approaches. Last fall, several components of MTF
technology were demonstrated. Los Alamos, in collaboration with the Air Force
Research Laboratory, now leads a project to develop the preheated plasma needed for
MTF. Researchers subsequently hope to conduct an experiment that will test this
preheated plasma along with components of the implosion system. Papers GP1.074,
MP1.119, MP1.120, others - Contact Glen Wurden, Los Alamos (505-667-5633,
wurden@lanl.gov),
Richard E. Siemon, Los Alamos
(rsiemon@lanl.gov); see
http://fusionenergy.lanl.gov)
Design for magnetized target fusion (MTF) device.
6. Plasmas Can Focus High Energy Beams
Hector Baldis of Livermore (925-422-0101,
baldis1@llnl.gov)
will show that plasmas
can focus high-density, high-energy (30 GeV) electron and positron beams 1000 times
better than the magnetic quadrupoles used in conventional accelerator technology. In the
E150 experiment
(http://www.slac.stanford.edu/exp/e150/)
carried out at the SLAC Final
Focus Test beam, a plasma could focus an electron beam to one third of its original
diameter in just 2 centimeters. In addition, the researchers demonstrated plasma focusing
of high-energy positron beams for the first time. Technologies have existed for focusing
MeV electron beams, but not for the GeV beams that will be used in future accelerator
experiments. This work demonstrates a potentially promising technique for focusing
those GeV beams. The plasma's focusing effect was anticipated in earlier theoretical and
experimental research, but not demonstrated until now. How does a plasma focus particle
beams so well? To understand this effect, it is important to realize that electrons, or other
electrically charged particles, in a beam experience two competing forces: a repulsive
"Coulomb" force which tries to make the beam blow apart, and magnetic forces which
push the electrons together. As it passes through a plasma, the high energy beam will
redistribute the electrons so that the net Coulomb force is decreased but the magnetic
force is not affected; this serves to pinch the beam closer together. Conventional plasmas
seem to focus the beams very well; no exotic plasmas must be prepared. (Paper
BO2.002)
Diagram of the E150 plasma lens experiment at the Stanford Linear Accelerator Center
(SLAC), along with a schematic of the plasma lens itself.
7. The Process of Magnetic Reconnection Underlies Events in the Sun's Corona and
Helps Drive Current in the National Spherical Torus Experiment
Researchers will present some of the first physics results from the National Spherical
Torus Experiment (NSTX), the new magnetic fusion device at the Princeton Plasma
Physics Laboratory. It is called a "spherical torus" (ST) because the surface of the
plasma in it is shaped like a sphere with a narrow hole through the center. To maintain
plasma confinement in an ST and to help heat the plasma, a strong electric current,
encircling the central hole, must be driven in the plasma. In December 1999, NSTX
reached a primary design goal by operating with one million amperes of current induced
in the plasma by a solenoid (a spool-shaped coil) passing through the central hole. In
addition to this traditional way of driving the plasma current, the researchers are
developing a new method for producing this current. Known as coaxial helicity injection
(CHI), this technique involves injecting an electric current directly from coaxial circular
electrodes inside the plasma chamber, in the presence of an applied magnetic field. A
picture of the plasma inside NSTX during CHI is shown in Fig. 1.
The magnetic field causes the injected current to wrap many times around central column in its passage between the electrodes, so the current can be many times that injected, as shown in Fig. 2.
The current loops formed during CHI have similarities to the coronal loops seen on the sun's outer surface during solar flares. Just as in the solar corona, these loops can become unstable and relax to a lower energy state through a process known as magnetic reconnection. In the case of the ST, this lower energy state is one in which some of the current flows on field lines which close on themselves inside the vessel to form a confined plasma core. Whereas the traditional technique of inducing the current with a solenoid can only produce brief bursts of plasma current in an ST, the CHI technique holds promise for helping them to operate continuously, as needed for a future fusion reactor. The NSTX experiments build on earlier work by Prof. Tom Jarboe and his team at the University of Washington in the Helicity Injected Torus (HIT). Roger Raman (raman@aa.washington.edu), Dennis Mueller (dmueller@pppl.gov), and Dave Gates (dgates@pppl.gov) led the CHI experiments on NSTX. For details see paper BO1.004 by R. Raman and others. Contact Martin Peng, NSTX Program Director (1-609-243-2305, mpeng@pppl.gov) for information concerning the research program on the NSTX.
A movie of a plasma during coaxial helicity injection (CHI).
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