Open ended axially symmetric systems. Results and perspectives
Significant progress of the simplest axisymmetric magnetic systems for plasma confinement and heating is described. Two of such systems are presented in this paper: multi mirror (GOL-3) and gas dynamic (GDT) traps. In the GOL-3 case the temperatures Te ≈ Е ≈ 2 keV were obtained in a dense (of or...
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Burdakov, A.V. Ivanov, A.A. Kruglyakov, E.P. 2015-05-20T15:21:42Z 2015-05-20T15:21:42Z 2006 Open ended axially symmetric systems. Results and perspectives / A.V. Burdakov, A.A. Ivanov, E.P. Kruglyakov // Вопросы атомной науки и техники. — 2006. — № 6. — С. 29-33. — Бібліогр.: 26 назв. — англ. 1562-6016 PACS: 52.55.Jd https://nasplib.isofts.kiev.ua/handle/123456789/81772 Significant progress of the simplest axisymmetric magnetic systems for plasma confinement and heating is described. Two of such systems are presented in this paper: multi mirror (GOL-3) and gas dynamic (GDT) traps. In the GOL-3 case the temperatures Te ≈ Е ≈ 2 keV were obtained in a dense (of order of 10²¹m⁻³) plasma and the maximum value of nIJE ≈ 2·10¹⁸m⁻³s was achieved. Any physical limitations which could prevent from further grow of plasma parameters did not find out. The most important results obtained in the experiments on GDT are described. A new step (GDT-U) has been prepared and the first preliminary experiments with quasi-stationary plasma heating have started. According to calculations, the parameters of the GDT-U should demonstrate the feasibility of “moderate” (0.5 MW/m²) 14 MeV neutron source for structural materials tests of fusion reactor. en Національний науковий центр «Харківський фізико-технічний інститут» НАН України Вопросы атомной науки и техники Magnetic confinement Open ended axially symmetric systems. Results and perspectives Article published earlier |
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Open ended axially symmetric systems. Results and perspectives |
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Open ended axially symmetric systems. Results and perspectives Burdakov, A.V. Ivanov, A.A. Kruglyakov, E.P. Magnetic confinement |
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Open ended axially symmetric systems. Results and perspectives |
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open ended axially symmetric systems. results and perspectives |
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Burdakov, A.V. Ivanov, A.A. Kruglyakov, E.P. |
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Burdakov, A.V. Ivanov, A.A. Kruglyakov, E.P. |
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Magnetic confinement |
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Magnetic confinement |
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Вопросы атомной науки и техники |
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Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
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Significant progress of the simplest axisymmetric magnetic systems for plasma confinement and heating is
described. Two of such systems are presented in this paper: multi mirror (GOL-3) and gas dynamic (GDT) traps. In the
GOL-3 case the temperatures Te ≈ Е ≈ 2 keV were obtained in a dense (of order of 10²¹m⁻³) plasma and the maximum
value of nIJE ≈ 2·10¹⁸m⁻³s was achieved. Any physical limitations which could prevent from further grow of plasma
parameters did not find out. The most important results obtained in the experiments on GDT are described. A new step
(GDT-U) has been prepared and the first preliminary experiments with quasi-stationary plasma heating have started.
According to calculations, the parameters of the GDT-U should demonstrate the feasibility of “moderate” (0.5 MW/m²)
14 MeV neutron source for structural materials tests of fusion reactor.
|
| issn |
1562-6016 |
| url |
https://nasplib.isofts.kiev.ua/handle/123456789/81772 |
| citation_txt |
Open ended axially symmetric systems. Results and perspectives / A.V. Burdakov, A.A. Ivanov, E.P. Kruglyakov // Вопросы атомной науки и техники. — 2006. — № 6. — С. 29-33. — Бібліогр.: 26 назв. — англ. |
| work_keys_str_mv |
AT burdakovav openendedaxiallysymmetricsystemsresultsandperspectives AT ivanovaa openendedaxiallysymmetricsystemsresultsandperspectives AT kruglyakovep openendedaxiallysymmetricsystemsresultsandperspectives |
| first_indexed |
2025-11-27T04:08:50Z |
| last_indexed |
2025-11-27T04:08:50Z |
| _version_ |
1850799030106324992 |
| fulltext |
Problems of Atomic Science and Technology. 2006, 6. Series: Plasma Physics (12), p. 29-33 29
OPEN ENDED AXIALLY SYMMETRIC SYSTEMS.
RESULTS AND PERSPECTIVES
A.V. Burdakov, A.A. Ivanov, E.P. Kruglyakov
Budker Institute of Nuclear Physics, 630090, Novosibirsk, Russia
Significant progress of the simplest axisymmetric magnetic systems for plasma confinement and heating is
described. Two of such systems are presented in this paper: multi mirror (GOL-3) and gas dynamic (GDT) traps. In the
GOL-3 case the temperatures Te 2 keV were obtained in a dense (of order of 1021m-3 ) plasma and the maximum
value of n E 2·10 18m- 3s was achieved. Any physical limitations which could prevent from further grow of plasma
parameters did not find out. The most important results obtained in the experiments on GDT are described. A new step
(GDT-U) has been prepared and the first preliminary experiments with quasi-stationary plasma heating have started.
According to calculations, the parameters of the GDT-U should demonstrate the feasibility of “moderate” (0.5 MW/m2)
14 MeV neutron source for structural materials tests of fusion reactor.
PACS: 52.55.Jd
INTRODUCTION
At present, the Budker Institute runs two large scale
axisymmetric mirror experiments of different type. The first
one is a multi mirror system (GOL-3) and the second is gas
dynamic trap (GDT). Principle of multi-mirror plasma
confinement was proposed by Budker, Mirnov and Ryutov
[1] in early 70s. The first successful experiments to prove the
idea were done with a rare alkaline plasma in the period
1973-75 [2]. According to the initial idea [3] the multi-mirror
reactor should operate with a dense (order of 1024m-3) plasma
confined by strong (order of 10T) magnetic field. The plasma
should be heated by powerful relativistic electron beam
(REB). The main requirements of the theory of multi mirror
plasma confinement [1] can be met for the dense plasma if
the reactor has several hundred meters in length. The
magnetic field even being as strong as 10T is too small to
provide transverse plasma confinement. In order to overcome
this difficulty it was proposed to use material wall to
withstand plasma pressure whereas radial energy losses are
being controlled by the magnetic field (so called “wall
confinement”) [4]. Another problem of the multi mirror
reactor is how to provide efficient plasma heating. The first
experiments on study of REB – plasma interaction were
begun in 1972 [5]. They indeed have demonstrated that
plasma can be efficiently heated under certain conditions. In
the first experiments the total beam energy amounted to only
50 J. In the present experiments at the GOL-3 device total
energy of REB exceeds this level by almost four orders of
magnitude. As a result of this increase, many new
phenomena were recently discovered on GOL-3. In
particular, for the first time an effect of strong (by three
orders of magnitude) suppression of longitudinal electron
heat conduction was observed [6]. Correspondingly, high
electron temperature amounting to several keVs was reached
[7]. In the case of multi-mirror configuration fast ion heating
up to 2 keV was also observed [8]. Besides, it turned out that
the heating and confinement of ions are significantly more
effective than that one could expect using the estimates based
on binary Coulomb collisions theory. Indeed, it is shown that
there exists a mechanism of enhanced scattering of axially
moving ions which leads to their trapping into the mirror
cells and to corresponding increase of their longitudinal
confinement time [9]. This suggests significantly wider range
of parameters for the reactor compare to the initial theory.
At present, the GOL-3 has extremely high energy density in
plasma flux exhaust which typically is in the range of
1…50 MJ/m2. This provides rather unique opportunity for testing
of structural materials for ITER and DEMO under effect of
energetic plasma flow with hot electrons.
The second system, the GDT [10], is essentially the
Budker-Post type mirror trap but with high mirror ratio
(R>1) and high enough plasma density so that effective
ion mean free path of scattering into loss cone ~ ii /R is
smaller than the length of the device - L. The reactor
based on the GDT concept seems to be very reliable
because in the collisional plasma micro instabilities do not
excite. However, such a reactor appears to be rather long,
order of ten kilometers, and its minimal power is
drastically high (order of 40 GW) [11]. Nevertheless,
there exists an intermediate important problem which can
be addressed with the aid of the GDT. In [12] an idea of
the GDT based 14 MeV neutron source was proposed. For
moderate plasma parameters the most crucial problems of
plasma confinement in the GDT based neutron source
have been already solved. In particular, strong
suppression of electron heat conductance to the end walls
by axial drop of the magnetic field has been
demonstrated [13]. The MHD-stable plasma confinement
in axisymmetric magnetic configuration of GDT was also
successfully demonstrated in the experiments [14-16]. In
the recent years, a lot of studies both theoretical and
experimental have been done to support the development
of the GDT based neutron source. Detailed description
of that activity can be found in [17]. Note that besides the
GDT NS many other schemes of neutron sources were
proposed in recent years. Comparison of other proposed
NSs with the GDT NS was presented in [18]. The analysis
shows that the GDT NS has a number of advantages in
comparison with other candidates to the role of the
neutron source for tests of structural materials of future
fusion reactor. In particular, among other candidates, the
GDT NS has the lowest power and tritium consumption.
At the same time, this source satisfies the requirements of
material scientists concerning to both: neutron flux
density (2 MW/m2 or 1014neutrons/cm2·s) and the testing
zone area (of the order of 1 m2).
30
One of the most important factors determined the lifetime
of fast ions in the GDT and the efficiency of neutron
production is the electron temperature. At present, in the GDT
experiments Te is limited to ~100 eV. This value is too low
for the neutron source. In the nearest future it is planned to
extend the NB duration from 1 up to 5 ms. According to
calculations, it will result in increase of Te up to 200 eV.
Additionally, installation of new injectors is planned with
increased injection power. They should be mounted on the
GDT in the end of this year. It follows from the calculations
that the electron temperature of 300 eV will be then obtained.
As soon as it happens this will demonstrate feasibility of the
neutron source with “moderate” neutron flux (~0.5MW/m2).
To demonstrate practicability of full scale NS the device
named “Hydrogen prototype” is planned to be constructed
later on.
GOL-3 EXPERIMENTS
Many efforts were put forth to come to present day status
of multi mirror machine studies. As to plasma heating by
REB is concerned, modern technology of high voltage
generators for REB production was developed stepwise
using intermediate generators of REB with water insulation
and with the REB energy of 1, 4 and 20 kJ. The present day
REB for the GOL-3 facility has the energy of the beam
electrons of 1 MeV and maximum beam current of 50 kA.
The duration of the REB pulse was most dramatically
changed amounting at present up to 8·10-6 s.
Among many devices designed and constructed in the
scope of the program of REB – plasma interaction study
one should mention GOL-M device. Unique diagnostics
based on registration of collective scattering of CO2 laser
radiation were worked out there. Using these it was
experimentally shown for the first time that Langmuir
turbulence is being excited as a result of the REB-plasma
interaction [19]. Later on [20] an excitation of ion-
acoustic turbulence was observed with a level of
oscillations exceeding by five orders of magnitude the
thermal one. The excitation of the ion-acoustic turbulence
in non-isothermal (Te/Ti >>1) plasma by REB can be
explained by a collapse of Langmuir waves in the case of
strong Langmuir turbulence. On the final stage of the
collapse, due to plasma density and pressure drop inside
and outside a cavity the short wave ion-acoustic waves
are excited. The phenomenon of the collapse in the case
of strong Langmuir turbulence has been observed
experimentally on the GOL-M device [21].
The first experiments have been done with plasma
(ne~1021m-3) placed in 7 m long solenoid with 5T
homogeneous magnetic field. In the end mirrors magnetic
field was 11T. The beam diameter in plasma was 6 cm.
These experiments have demonstrated high efficiency of
REB-plasma interaction. In optimal conditions the REB
energy losses in the plasma achieved up to 40%.
However, as it followed from estimation (see [6]), plasma
heating strongly increases Spitzer longitudinal thermal
conductance, so that the electron temperature cannot
exceed 100…150 eV for the given heating power. In fact,
the electron temperature achieved the level of Te~2 keV.
As calculations have shown this value of temperature is
only possible if the longitudinal thermal conductance of
the plasma is three orders of magnitude less than the
Spitzer one [6]. As it follows from the results obtained on
the GOL-M for the conditions similar to that on the GOL-
3 (except the beam duration), it can be explained by
enhanced scattering rate of plasma electrons due to
presence of relatively slow density fluctuations related to
ion-sound turbulence and collapsing cavities. Direct
experimental demonstration of the suppression of
longitudinal heat conductance was made on the GOL-3
[22]. For that, magnetic field in a section of solenoid was
decreased as it is seen in Fig.1.
Fig.1. Direct observation of anomalously low
longitudinal electron heat conductance during the
process of collective relaxation of REB in plasma
In minimum magnetic field the REB current density is
also minimal providing smaller energy release in this
region. Correspondingly, the electron temperature was
measured to be constant outside the local magnetic “well”
and high (Te ~ 1 keV). At the same time, it was
significantly less in the bottom of the well (Te~150 eV).
It should be noted that this very steep temperature
gradient is sustained during REB injection and disappears
immediately after switching off the beam.
More reach physics appears with the transition to
multi mirror geometry of the magnetic field. These
experiments were done with longer solenoid (12 meters).
The beam duration was 8·10-6 s (instead of 3·10-6 s in the
first experiments), there were 55 mirror cells with
Bmax= 5T and Bmin = 3.5 T. Typical plasma density was
varied in the range of (0.5…2) · 1021 m-3. After transition
from homogeneous magnetic field to multi mirror
configuration significant progress in the GOL-3
parameters was observed as it is seen in Fig.2. Energy
confinement time was increased by two orders of
magnitude. Recently the energy confinement time
exceeded 10-3 s at the density level of order of 1021 m-3.
It has been already mentioned that after switching off the
REB current the effect of suppression of electron thermal
conductance disappeared immediately. As a consequence
of that the electron temperature of plasma fell down rather
quickly. Thus, the diamagnetic signal observed on the
upper trace of Fig. 2 can be explained by high ion
temperature. This result is rather unexpected. In the
process of REB-plasma interaction only plasma electrons
can be directly heated. The ions stay cold because the
temperature equilibration time is much longer than the
energy confinement time. Nevertheless, three independent
methods of measurements of the ion temperature which
were applied (besides diamagnetism) have shown that
31
plasma ions were heated rather fast (within tens of
microseconds) and the level of the ion temperature could
be estimated as 2 keV at plasma density ne ≅ 1021m-3 [23].
03
P
O
00
6F
0 0.2 0.4 0.6 0.8
time, ms
0
0.4
0.8
1.2
1.6
n e
T e
+n
iT
i,
10
15
ke
V/
cm
3
pl5871
0 0.2 0.4 0.6 0.8
time, ms
ne
ut
ro
n
flu
x,
cm
-2
s-1 1010
107
109
108
0 0.2 0.4 0.6 0.8
time, ms
ne
ut
ro
n
flu
x,
cm
-2
s-1 1010
107
109
108
Fig.2. Multi mirror system GOL - 3. Comparison of
temporal variation of plasma pressure and neutron flux.
deuterium density is 1.5·1021 m-3, z = 2.08 m from the
injection point
The ion temperature was measured by measurement of
Doppler broadening of Dα line at the boundary of hot
plasma, by registration of charge exchange neutrals from
hot plasma and by measurement of D-D neutron flux. All
the methods have shown that high ion temperature
reached the level of 2 keV within tens of microseconds.
As it is seen in Fig.2 (bottom part), the neutron yield falls
down very slowly and exists during the time scale of the
order of 10-3 s. The maximum value of n product, at
present, has achieved the level of ~ 2·1018 m-3s.
Possible mechanism of ion heating can be
qualitatively explained as follows. During REB-plasma
interaction in corrugated magnetic field the electron
heating is strongly non uniform. The strongest heating of
electrons should take place at the maxima of magnetic
field where the REB current density is maximal. As a
result, the electron pressure will be higher there and will
be lower in the mid planes of each mirror cell (see Fig.1).
These pressure drops are sustained by the REB.
As it has already mentioned, the longitudinal heat
transfer is suppressed till the switching off the REB. After
that the effective collision frequency of electrons falls
down roughly by thousand times and the expansion of
high pressure plasma clouds initially localized near
mirrors and containing hot electrons together with cold
ions will produce the counter fluxes of plasma with shock
waves collisions and subsequent conversion of energy of
directed movement into ion heating. Note that there is an
additional effect which leads to shortening of effective ion
mean free path and to increase of the longitudinal
confinement time.
Regular oscillations of the neutron flux irradiated
from single mirror cell can be observed practically during
all the confinement time [24]. The period of these
oscillations is of order of l/vi , where l is a single cell size
and vi is ion thermal velocity. In principle, electrostatic
plasma oscillations with phase velocities of the order of vi
experience strong dumping and can not exist for the case
Te< Ti . Nevertheless, they were observed experimentally
and corresponded well to bounce frequency of ions. This
contradiction can be explain by the fact that plasma in the
multi mirror geometry is not homogeneous and the
distribution function is non-equilibrium. In this case,
bounce oscillations can exist in separate cells and play
very useful role for improvement of longitudinal plasma
confinement. Transit ions passing through a cell will
scattered on the bounce oscillations and become trapped.
Thus, an effective mean free path can be significantly
reduce. For more details see [9].
In principle, axisymmetric multi mirror magnetic
system is MHD unstable. However, as it was
experimentally demonstrated in [22] there is a method of
plasma stabilization in the sense of MHD.
The present day parameters of the GOL-3 makes it
possible to model not only evaporation, ionization and
destruction of wall materials in the case of Edge
Localized Modes (ELMs) in tokamaks but also to study
the impurity ion propagation along magnetic field lines.
The level of energy density in the plasma flux is so high
(1…50 MJ/m2) that enables to study even plasma – wall
interaction during major disruptions. It is important that
the GOL-3 plasma has hot electrons and ions. At present,
there is no other system to model hot electron plasma
wall interaction in ITER and DEMO. For more detailed
information see [ 25].
GAS DYNAMIC TRAP (GDT)
Advantages of the GDT approach stem from very
simple and reliable physics of longitudinal plasma
confinement and from axial symmetry of the system. In
contrast to the conventional mirrors, because of high
mirror ratio and narrow loss cone, the collisional plasma
confined in the trap is very close to isotropic Maxwellian
state, and, therefore, many instabilities, which are
potentially dangerous for the classical magnetic mirrors,
can not excite in the regime of gas dynamic plasma
confinement. Very simple consideration shows that the
longitudinal confinement time in the device can be
estimated as τ ≈ R⋅L/VTi and it appears to be proportional
to the mirror ratio R and length L of the trap. The
confinement time seems too small for fusion reactor, but,
it is quite appropriate in the case of neutron source (NS)
GDT based. The key element of the NS is the powerful
oblique injection of neutral beams into “warm” plasma
and formation there fast deuterons and tritons oscillating
between turning points. The density of these anisotropic
ions has strong maxima near the turning points.
Correspondingly, the neutron flux maxima appear at the
same places. According to our calculations, the GDT NS
can produce the neutron flux density of 2 MW/m2
(1014 neutrons/cm2·s) at the area of 1 m2. At present, the
main physical problems of the gas dynamic plasma
confinement have already been solved, at least for
moderate plasma parameters. In particular, it was shown
that in spite of unfavorable curvature of magnetic field
lines in the trap the plasma can be stabilized against
excitation of MHD modes. It was shown experimentally
that high enough favorable curvature of the field lines in
the expander region beyond the mirrors stabilize the entire
plasma [14]. The stability can be made significantly more
rigid if additional cusp end cell is attached to the central
32
solenoid of GDT [15]. At last, it should be mentioned
that an influence of radial electric fields on transverse
plasma losses was observed [16].
Another important problem for the GDT is longitudinal
electron thermal conductivity. It was shown
experimentally that if the magnetic field drops between
mirror and end wall so that the ratio of Bm /Bw is larger
than (M/m)1/2 ~45 for hydrogen, axial electron conduction
is suppressed and there is no influence of the end wall
position on the electron temperature in the trap [13].
Formation of the peaks of D-D neutron yield near the
ion turning points have been demonstrated in the
experiments with injection of deuterium beams into GDT,
with complete agreement with simulation results [26].
All these experiments carried out with the following
parameters of the device. The mirror to mirror distance is 7
meters, plasma radius at the mid plain is 8…15 cm, magnetic
field value in the mirrors is up to 15 T, and in the mid plane is
0.22 T. Plasma density is 3…20·1019m-3. The parameters of
NB injectors are: the beam energy Eb = 15…17 keV, total
injection power is up to Pb = 4 MW, the beam duration,
τb = 1.1 ms, and the injection angle is 450. At these parameters
the electron temperature of order 100 eV was obtained. This
value is in a reasonable agreement with calculation results.
Nevertheless, it is quite far from that required for
demonstration of practicability of full scale GDT NS. At
present, new injectors and new power supplies for them are
under construction. The comparison of the present day GDT
and the GDT upgrade parameters is given in the Table below.
GDT 2003 GDT-U
Injection energy 15…17 keV 25 keV
Power 4MW 9-10MW
Duration 1ms 5ms
Magnetic field at
mid-plane
0.23T 0.3T
Electron temperature ~100eV ~300eV
Plasma density 4 ⋅1019 m-3 4 ⋅1019 m-3
Fast ion density 2 ⋅1019 m-3 5 ⋅1019 m-3
Average energy 8-10 keV 10-15 keV
Longer duration of neutral beam injection from
physical view point corresponds to the regime of steady
state operation. The experiments on the GDT-U are
planned to start in autumn of 2006.
Fig.3. Electron temperature variation during time. Upper
trace-10 MW, lower trace – 4 MW of injection power
It is seen in Fig.3 that, at present, the plasma of GDT does
not reach steady state during the injection pulse.
According to calculations, simple increase of the injection
duration should double the electron temperature.
If the value of Te=300 eV predicted by the code will be
obtained, it will prove that “moderate” NS with neutron
flux density of 0.5 MW/m2 (2.5·1013neutrons/s·cm2) is
feasible. On the other hand, the distance between
achieved (Te = 300 eV) and required (Te=750 eV) for full
scale NS temperature will be small enough and degree of
confidence to the simulation results becomes higher. At
present, the activity connected with completion of
construction of hydrogen prototype as a model of the full
scale neutron source is re-started in Novosibirsk.
CONCLUSIONS
Taking into account recent successes of the GOL-3 on
heating and confinement of a dense plasma, one can say
that axisymmetric multi mirror system, attractive by its
engineering simplicity, in principle, has perspectives as a
fusion reactor with magnetic (but not “wall”) confinement
of plasma. High power relativistic electron beam looks as
a realistic source of energy for this scheme.
Recent status of GOL-3 and under-discussion upgrade
makes this facility very important for structural materials
tests on resistance to high heat fluxes of electronic-hot
plasma. Besides, a propagation of cloud of impurities
formed as a result of disruption or ELM activity along and
across magnetic field can be studied in this trap.
Very promising results can be obtained at the GDT in
the nearest time. Till the end of 2006 it should be
demonstrated with high probability the practicability of
“moderate” neutron source. In the case of success, the
modeling of the full scale neutron source would start
soon. To our opinion, even “moderate” NS with large
(~1m2) size of testing zone could be very useful for
material scientists. At present, they have nothing similar
to the NS under discussion. Correspondingly, even
DEMO can not be built without testing of materials.
REFERENCES
1.G.I.Budker, V.V.Mirnov, D.D.Ryutov. Influence of corrugated
magnetic field on expansion and cooling of plasma // Sov. JETP
Lett, 1971, v.14, #5, p.320.
2.G.I.Budker, V.V.Danilov, E.P.Kruglyakov. Experiments on
plasma confinement in multi mirror trap // Sov JETP. 1973,
v.65, #2(8), p.562; V.V.Danilov, E.P.Kruglyakov. Dynamics of
plasma in multi mirror magnetic system // Sov. JETP, 1975,
v.68, #6, p.2109.
3.G.I.Budker, E.P.Kruglyakov, V.V.Mirnov, D.D.Ryutov. On
the possibility of creation of thermonuclear reactor with a dense
plasma, confined by corrugated magnetic field // Izvestia AN
SSSR, Energetika i Transport. 1975, #6, p.35 (in Russian).
4.G.E.Vekshtein, D.D.Ryutov, M.D.Spektor, P.Z.Chebotaev.
Nonmagnetic confinement of dense plasma // Prikladnaya
Mekhanika i Tekhnicheskaya Fizika (Journ. of Appl. Mech. and
Tekhn. Phys), 1974, #6, p.3.
5.A.V.Abrashitov, A.V.Burdakov, V.S.Koidan, et al. Plasma
heating by relativistic electron beam // Sov JETP Lett. 1973,
v.18, p.675.
6.V.T.Astrelin, A.V.Burdakov, V.V.Postupaev. Generation of
ion-acoustic waves and suppression of heat transport during
plasma heating by an electron seam. Plasma Phys. Reports.
1998, v.24, #5, p.414.
7.A.V.Burdakov, S.G.Voropaev, V.S.Koidan et al. Experiments
on collective interaction of microsecond relativistic electron
33
beam with plasma on GOL-3 // Rus. JETP. 1996, v.109, #6,
p.2078.
8.R.Yu.Akentjev, A.V.Arzhannikov, V.T.Astrelin et al.
Experimental results on multiple mirror trap GOL-3 // The 29th
EPS Conf. on Plasma Phys. and Contr. Fusion, Montreux, 17-21
June 2002. ECA, 2002, v.26B, P5-057.
9. A.D. Beklemishev. Bounce Instability in a Multi Mirror Trap
// Proceedings of the OS 2006 Conference, 17-21 July, 2006,
Tsukuba, Japan
10. V.V. Mirnov, D.D. Ryutov. Linear gas-dynamic trap for
plasma confinement // Sov. JETP Lett, 1979, v.5, #11, p.678.
11. H.H. Hennies, E.P. Kruglyakov, D.D. Ryutov. The gas
dynamic trap (GDT)-system as a promising engineering solution
for a volumetric neutron sourse and an intermediate step to a
fusion reactor // The 9th Intern. Conf. on Emerging Nuclear
Energy Systems (ICENES’98), Herzliya, Israel, June 28 – July
2, 1998
12.I.A. Kotelnikov, V.V. Mirnov, V.P. Nagornyj, D.D. Ryutov.
New results of gas-dynamic trap research // Plasma Phys. and
Controlled Fusion Res., Vienna, IAEA, 1985, v.2, p.309.
13.A.V.Anikeev, P.A.Bagryansky, N.V.Stupishin. Longitudinal
confinement of matter and energy in gas-dynamic trap // Plasma
Phys. Reports. 1999, v.25, #10, p.842.
14. A.A. Ivanov, P.A. Bagryansky, A.V. Anikeev et al.
Experimental study of curvature driven flute instability in the
gas-dynamic trap// Phys.of Plasmas. 1994, 1, #5, part 2, p.1529.
15. A.V. Anikeev, P.A. Bagryansky, P.P. Deichuli et al.
Observation of magnetohydrodynamic stability limit in a cusp
anchored gas dynamic trap// Phys.of Plasmas, 1997, v.4,
p.347.
16. P.A. Bagryansky, A.A. Lizunov, A.A. Zuev. Experiments
with controllable application of radial electric fields in GDT
central cell// Trans. of Fusion Sci. and Techn. 2003, v.47, #1T,
p.152.
17. P.A. Bagryansky, A.A. Ivanov, E.P. Kruglyakov et al. Gas
dynamic trap as high power 14 MeV neutron source // Fusion
Engineering and Design. 2004, v.70, p.13.
18. E.P. Kruglyakov. Powerful neutron generators // Journ. of
Appl. Mechanics and Techn. Phys. 1997, #4, p.566.
19. I.V. Kandaurov, E.P. Kruglyakov, M.V. Losev et al. CO2
laser scattering on Langmuir electron plasma waves excited by
REB // Proc. ICPP, Nov. 22-28, 1989, New Delhi. v.3, p.1121;
L.N. Vycheslavov, I.V. Kandaurov, E.P. Kruglyakov. Direct
observation of Langmuir turbulence in plasma by method of
laser scattering // Sov.JETP Lett. 1989, v.50, #9, p.379.
20. V.S. Burmasov, I.V. Kandaurov, E.P. Kruglyakov et al.
Observation of short-wavelength ion acoustic waves
accompanying strong Langmuir turbulence in a magnetized
plasma // The 22nd EPS Conf. on Plasma Phys. and Contr.
Fusion, 3-7 July, 1995, Bornemouth, UK. v.19C, part 1, p.445.
21. V.S. Burmasov, I.V. Kandaurov, E.P. Kruglyakov et al.
Manifestation of wave collapse in developed strong Langmuir
turbulence in a magnetic field // The 23rd EPS Conf. on Plasma
Phys. and Controlled Fusion, 24-28 June, 1996, Kiev, Ukraine
v.20C, part 3, p.1253.
22. A.V. Burdakov, A.V. Arzhannikov, A.T. Astrelin et al. Fast
heating of ions in GOL-3 multi mirror trap // The 31st EPS Conf.
on Contr. Fus.and Plasma Phys., 28 June-2 July, 2004, London.
23.V.S. Koidan, A.V. Arzhannikov, V.T. Astrelin et al. Progress
on the multi mirror trap GOL-3 // Trans. of Fusion Science and
Technology. 2005, v.47, #1T, p.35.
24. A.V. Burdakov, A.V. Arzhannikov, V.T. Astrelin et al.
Stable operation regimes in the multi mirror trap GOL-3 // The
32nd EPS Conf. on Controlled Fusion and Plasma Physics, June
27-July 1, 2005, Tarragona, Portugal. v.27A, P5-061.
25. A.V.Burdakov, A.V.Arzhannikov, V.T.Astrelin et al.
Testing of carbon materials for fusion applications on linear
plasma trap GOL-3 // European Congress on Advanced
Materials and Processes, Prague, 5-8 September, 2005.
26. V.V. Maximov, A.V. Anikeev, P.A. Bagryansky et al.
Spatial profiles of fusion product flux in the gas dynamic trap
with deuterium neutral beam injection // Nucl.Fus. 2004, v.44,
N4, p.542.
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