Steady-state fusion fission reactor concepts based on stellarator-mirror and mirror machines
Neutron sources and hybrid reactors offer a possibility for application of fusion in a not too distant future. Steady-state operation on a time scale of a year without interruption is essential for such applications. In response to this need, our studies are focused on concepts which are not limited...
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| Date: | 2015 |
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Національний науковий центр «Харківський фізико-технічний інститут» НАН України
2015
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| Cite this: | Steady-state fusion fission reactor concepts based on stellarator-mirror and mirror machines/ O. Ågren, V.E. Moiseenko, K. Noack, S.V. Chernitskiy // Вопросы атомной науки и техники. — 2015. — № 1. — С. 3-7. — Бібліогр.: 21 назв. — англ. |
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Digital Library of Periodicals of National Academy of Sciences of Ukraine| _version_ | 1859666684466429952 |
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| author | Ågren, O. Moiseenko, V.E. Noack, K. Chernitskiy, S.V. |
| author_facet | Ågren, O. Moiseenko, V.E. Noack, K. Chernitskiy, S.V. |
| citation_txt | Steady-state fusion fission reactor concepts based on stellarator-mirror and mirror machines/ O. Ågren, V.E. Moiseenko, K. Noack, S.V. Chernitskiy // Вопросы атомной науки и техники. — 2015. — № 1. — С. 3-7. — Бібліогр.: 21 назв. — англ. |
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| container_title | Вопросы атомной науки и техники |
| description | Neutron sources and hybrid reactors offer a possibility for application of fusion in a not too distant future. Steady-state operation on a time scale of a year without interruption is essential for such applications. In response to this need, our studies are focused on concepts which are not limited by pulsed operation. Special attention is put on mirror machines and a stellarator-mirror concept with localized neutron production. Reactor safety, magnetic coils, power amplification by fission, plasma heating, a radial constant of motion which provides a bounded radial motion in the collision free approximation are some of the issues addressed.
Источники нейтронов и гибридные реакторы предоставляют возможность применения термоядерного синтеза в не слишком отдаленном будущем. Стационарный режим работы без перерывов необходим для таких устройств. В ответ на эту потребность наши исследования сосредоточены на концепциях, которые не ограничиваются работой только в импульсном режиме. Особое внимание уделяется пробкотронным устройствам и концепции стелларатора-пробкотрона, которые характеризуются локализованным излучением нейтронов. Рассмотрены вопросы безопасности реактора, формы магнитных катушек, усиления мощности за счет реакции деления, нагрева плазмы и роли радиального инварианта движения ионов, который обеспечивает удержание ионов при их радиально колебательном движении в бесстолкновительном приближении.
Джерела нейтронів і гібридні реактори надають можливість застосування термоядерного синтезу в не занадто віддаленому майбутньому. Стаціонарний режим роботи без перерв потрібний для таких пристроїв. У відповідь на цю потребу наші дослідження зосереджені на концепціях, які не обмежуються роботою тільки в імпульсному режимі. Особлива увага приділяється пробкотронним пристроям і концепції стеларатора-пробкотрона, які характеризуються локалізованим випромінюванням нейтронів. Розглянуті питання безпеки реактора, форми магнітних котушок, посилення потужності за рахунок реакції ділення, нагріву плазми і ролі радіального інваріанту руху іонів, який забезпечує утримання іонів при їх радіально коливальному русі в беззіштовхувальному наближенні.
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| first_indexed | 2025-11-30T11:28:11Z |
| format | Article |
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MAGNETIC CONFINEMENT
ISSN 1562-6016. ВАНТ. 2015. №1(95)
PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. 2015, №1. Series: Plasma Physics (21), p. 3-7. 3
STEADY-STATE FUSION FISSION REACTOR CONCEPTS BASED
ON STELLARATOR-MIRROR AND MIRROR MACHINES
O. Ågren
1
, V.E. Moiseenko
2
, K. Noack
1
, S.V. Chernitskiy
2
1
Uppsala University, Ångström Laboratory, Uppsala, Sweden;
2
National Science Center ‘‘Kharkov Institute of Physics and Technology”, Kharkov, Ukraine
Neutron sources and hybrid reactors offer a possibility for application of fusion in a not too distant future. Steady-
state operation on a time scale of a year without interruption is essential for such applications. In response to this
need, our studies are focused on concepts which are not limited by pulsed operation. Special attention is put on
mirror machines and a stellarator-mirror concept with localized neutron production. Reactor safety, magnetic coils,
power amplification by fission, plasma heating, a radial constant of motion which provides a bounded radial motion
in the collision free approximation are some of the issues addressed.
PACS: 52.65.Сс, 52.55.Hc, 28.50.Ft
INTRODUCTION
The stellarator and straight field line mirror (SFLM)
hybrid reactor studies aim to identify a concept where the
safety of fission power production could be enhanced. A
fusion neutron source could become a mean to achieve
this. The studies address critical issues such as reactor
safety, natural circulation of coolants, steady-state
operation for a year or more and means to avoid too
strong material loads by a proper geometrical arrangement
of the reactor components. A key result is that power
production may be possible with a fusion Q factor as low
as 0.15. This possibility arises from the high power
amplification by fission, which within reactor safety
margins may be larger than a factor of 100. The
requirements on electron temperature, which is a critical
issue for mirror machines, are dramatically lower for a
fusion hybrid compared to a stand-alone fusion reactor.
This and several other factors are important for our choice
to select a stellarator-mirror or a mirror machine for the
fusion hybrid reactor studies. The basic design in our
mirror-machine studies (Fig. 1) is for a 1.5 GWth reactor
with a 25 m long plasma confinement region, 40 cm
plasma radius and only 10 MW fusion power [2, 3]. The
stellarator-mirror concept is outlined in Fig. 2.
In several ways (material loads, demands for plasma
confinement, size of fusion device and cost) a hybrid
reactor offers increased flexibility for power production
compared to a fusion reactor [1]. A disadvantage is the
substantial amount of radioactive materials in a hybrid
reactor.
The SFLM concept is outlined in Fig. 1. The stellarator-
mirror concept is shown in Fig. 2. A local mirror can be
created by turning off a toroidal field coil, providing a
local mirror field. The intention is to confine hot ions in
this mirror region. An advantage with a toroidal device is
the possibility to avoid longitudinal losses, which is a
serious obstacle for open devices.
A first goal with the hybrid reactor concepts are [2, 3] to
develop a fast reactor concepts with enhanced reactor
safety and incineration capacities. A second goal is to
define a concept where the demands on plasma
confinement, technical feasibility etc. are reachable. A
third goal is to define a concept where material loads are
tolerable. Finally, energy production in steady-state (for a
year or more) would be necessary from technological
and economic considerations.
Fig. 1. Outline of an SFLM hybrid reactor.
Feeding for RF heating, plasma diagnostics and
fusion neutron monitoring is through holes in the end
openings. Magnetic coils are shown, and the fission
reactor is located in between the coils and the
vacuum chamber for the fusion plasma
A magnetic configuration of a stellarator with an
embedded magnetic mirror has been arranged in the
Uragan-2M experimental device, which has separate
feeding for the helical and toroidal fields. Switching
off one toroidal coil or lowering the electric current
in the pair of neighboring coils creates a magnetic
mirror section with a mirror ratio around 1.5.
Regions with nested magnetic surfaces exist under
certain conditions in such a combined magnetic trap.
4 ISSN 1562-6016. ВАНТ. 2015. №1(95)
Fig. 2. Outline of the stellarator-mirror neutron source
with a fission reactor mantle. Fusion neutron production
is localized to the mirror part. All sensitive equipment are
also in this concept protected from strong neutron
bombardment
NUCLEAR SAFETY
An external neutron source added to a fast reactor could
contribute to reactor safety for several reasons: in a driven
system, the fission production can quickly be turned off.
For the SFLM, passive circulation is furthermore adequate
to remove decay heat [3, 6]. There are also other features
which could be favorable and make a driven system less
vulnerable to hazardous events.
The sub-criticality defines margins towards hazardous
events where the criticality for some reason is increased.
The SFLM safety has been tested against loss of coolant
scenarios (LOCA), void of coolant and partial
replacement of the eutectic lead-bismuth by water [4, 5].
In all cases studied, an SFLM reactor is predicted to
remain subcritical if the criticality keff in normal operation
is equal to or less than 0.97 (keff is the effective neutron
multiplication coefficient). If keff would be closer to unity,
the power from fission would be increased for a given
fusion power, but at the cost of a reduced margin for
nuclear safety [5].
PLASMA CONFINEMENT
A first requirement on any plasma device is that the
collision free motion is restricted to a region with the
confining magnetic field. A net radial drift out from the
confining field would lead to a rapid loss of particles. In
general quadrupolar mirrors, we have shown that radial
confinement could be assured by the existence of a radial
drift invariant in the form [7],
,r gc oscI r r (1)
where the first term is the guiding center radial coordinate
and the second terms represents oscillatory banana
excursions from the mean magnetic surface (these banana
widths are zero in a perfectly axisymmetric mirror). The
freedom to use biased potential endplates is a key for
radial confinement in open systems. The net radial drift in
quadrupolar mirrors can be eliminated in this way by
introducing a slow E B plasma rotation around the axis,
which can be controlled by the biasing potentials of the
end plates. Longitudinal confinement is assured by the
constancy of the energy and magnetic moment . The
existence of these three constants of motion provides
an excellent basis for confinement of particles in
mirror machines.
Small field errors (which could be associated
with the discrete nature of coils or other
disturbances) could produce a radial magnetic drift
and an unbounded radial motion. Such radial loss
could be cured by a radial electric field. This
favorable mechanism could be active in both
stellarators and mirror machines. An advantage with
the open mirror geometry is that the radial electric
field can be controlled by sectioned biased endplates.
No fusion device is yet close to the requirements
of a Q factor or 15 or more (which is necessary for
commercial power production). In a hybrid reactor,
the plasma confinement could be reduced
dramatically, if the power amplification from fission
is high enough. The geometrical arrangements of the
SFLM are intended to optimize the power
amplification, without jeopardizing nuclear safety.
For nuclear waste burning [5], the prediction for
power amplification in the SFLM is
4.5
150,
1
fis
fus eff
P
PAF
P k
(2)
where the upper bound is for keff =0.97, which is our
choice for upper bound on reactor safety. This
suggests that it could be possible to achieve a design
where fission exceeds the fusion power by more than
100 times with a sound margin for reactor safety.
During a full year operation, keff can slowly
decrease from its initial value 0.97. An average
power amplification around 100 is still plausible. For
power production, the demands on plasma
confinement can be reduced correspondingly, and a
Q factor as low as 0.15 could be sufficient for power
production [2, 4, 5]. This is welcoming news for
mirror machines, which are known to struggle with
the difficulty to reach sufficiently high electron
temperatures [8]. For a mirror hybrid, an electron
temperature as low as 800 eV (but preferably
somewhat higher, in the 1 keV range) can be
sufficient for power production [2-4]. Results in
recent years (for GOL-3 [9], GDT [10] and
Gamma10 [11]) indicate that electron temperatures
in this range could be reached in mirror machines.
Plasma stability is also addressed for the SFLM
[2, 3]. The average minimum B field (even without
expander tanks) provide gross MHD stability and
sloshing ions contribute to stability. Unlike the
axisymmetric GDT (Gas Dynamic Trap) the
expander tanks are not required for stability, since
the quadrupolar field in the SFLM is sufficient for
that purpose. The expander tanks with their 4 m radii
are merely included to provide a sufficiently large
area to withstand and distribute the heat from leaking
plasma. A power load less than 1 MW/m
2
is expected
for the SFLM “divertor” plates.
MATERIAL LOAD
The mirror machine and stellarator-mirror
concepts offer a geometrical flexibility to achieve
ISSN 1562-6016. ВАНТ. 2015. №1(95) 5
material loads within tolerable bounds. Diagnostic
windows and other sensitive equipment could be avoided
in the neutron rich region since the plasma column is
accessible beyond the fission mantle. The plasma heating
has been selected with care to avoid too strong material
loads. Antennas for ion cyclotron heating can be placed
near the maxima of the magnetic field, with good coupling
to the plasma. This enables shielding and feeding of the
antennas with due consideration of material load
limitations.
With a 10 MW fusion power and a Q factor of 0.15,
the expander tanks need to withstand a power around
60 MW, assuming a predominantly longitudinal plasma
loss. With an expander tank area of 100 m
2
(both sides
counted for), a power density of 0.6 MW/m
2
is well below
critical values. A representative ion gyro radius in the
weak field of the expander tanks is 0.5 m. The heat will
therefore be evenly distributed in the expander tanks.
Neutron bombardment on the first wall would pose
some problem if the buffer region in the fission mantle
would not have been included (this action increases the
wall life time by a factor of 4). With a buffer, the 200 dpa
threshold for the first wall requires more than 30 years for
its accumulation [4].
Monitoring of plasma and fusion neutrons is intended
with top view installations [12] (see Fig. 1). This choice is
made to avoid critical material loads. Monitoring of
fission neutrons is possible by detectors inside the fission
blanket surrounding the fusion device [12].
STEADY-STATE PLASMA MACHINES
Perhaps the most important reason to consider a mirror
machine or a stellarator-mirror device is that there is no
need for inductive current drive, whereby steady state
operation (for a year or more) may be feasible.
A better plasma confinement than in mirrors is
expected in a toroidal device, but a price is added
complexity. To avoid strong material loads, it is however
necessary to come up with a toroidal device proposal
where the neutron production is localized in a similar
manner as in the SFLM. For this reason, ideas have been
put forward for a stellarator-mirror hybrid [13]. The
intention is to achieve a fusion production localized to the
mirror segment of the device and to connect the mirror
ends with a stellarator tube [13] (a difference from the
toroidally linked mirror proposal in [14] is that the
stellarator part has a rotational transform).
Our designs consist of a comparatively small fusion
neutron sources (only about 10 MW fusion power), aimed
for 1.5 GWth power production, where the dominant part
comes from fission [1-3]. The role of the fusion part is
only to enhance reactor and nuclear safety and be able to
burn spent nuclear fuel, including minor actinides [2-4].
Some extra cost will arise from the fusion neutron source,
but the price would be dramatically lower than for a
fusion reactor. With such a small fusion device, the cost
for the power production would come closer to that of
conventional fission power.
GEOMETRICAL ARRANGEMENTS
A plasma with 40 cm radius is confined inside a
vacuum tube (radius 90 cm and length 25 m). The first
wall (3 cm wide) and a blanket with a buffer (15 cm
wide), the fission reactor core with fission fuel and
liquid lead bismuth eutectic coolant, core expansion
zone neutron radial reflector (60 cm wide) and a
tritium reproduction zone are located radially outside
the vacuum chamber, as indicated in Fig. 3. For the
nuclear waste burning application, the fuel consists
mainly of plutonium and minor actinide isotopes. To
avoid generation of minor actinide isotopes, the
U238 isotope is (apart from very small amounts) not
present in the blanket, and therefore the Doppler
broadening (which is of vital importance for the
reactor safety of fast reactors without an external
neutron source) is almost negligible. The blanket is
surrounded by superconducting coils with an inner
radius of 210 cm.
Fig. 3. Radial structure of the blanket model
The plasma losses are expected to be mainly axial,
and a sufficiently wide plate area is needed for taking
care of the losses. For this reason, flux tube expander
regions are located on each side beyond the 25 m
long confinement region. With a 10 MW fusion
power and Q around 0.15, the expander wall should
be capable to handle a power load in the range
60 MW. The 4 m wide expander tank radii provide
wide margins for the power load on the expander
plates.
RF antennas and their power feed can be located
in the high field region, where the neutron flux is
low. The ends of the confinement region could be
used for diagnostic purposes, refueling, ash removal
etc, and the geometry is selected to avoid holes in the
fission mantle. The geometry and the minimization
of holes in the fission core imply that most of the
fusion neutrons contribute to fission. Our concepts
have in this respect a better scaling than tokamaks.
Expander regions with favorable curvature add to
interchange stability, which is the key element for
stabilization of the axisymmetric GDT device, where
a stabilizing plasma flow into the expanders is
required. In the quadrupolar SFLM case, the
expanders are not necessary for MHD stability. The
sole purpose of the wide expander tanks is to provide
margins for the power load on the wall from leaking
plasma.
A design with superconducting 3D coils has been
carried out with a mirror ratio of 4 for the vacuum
field. The compact coil set has 3 m outer radius and
2.1 m inner radius. The coil inner radius is
sufficiently large to provide the required space for
the fission mantle. The coil computations take into
account the average minimum B stability criterion
and the transition to expander regions [15]. Particle
6 ISSN 1562-6016. ВАНТ. 2015. №1(95)
orbits, with emphasis on existence of nested magnetic
surfaces and radial confinement with closed mean drift
surfaces, have also been carried out for the stellarator
case. As already mentioned, a radial electric field can
have a favorable effect on confinement.
In the SFLM, the vacuum field lines [16, 17]
correspond to straight nonparallel lines (thus zero
curvature). The magnetic drifts are zero in the vacuum
field, but an azimuthal drift is present at finite beta, and
there is also a possibility to arrange a radial rotation
(which has a positive influence on confinement [10, 11]
by radial control plates in the expanders outside the
confinement region. Computations with compact 3D
superconducting coils have reproduced the SFLM field
with high accuracy. The coil computations also provide
“trumpet-like” expanders on each side of the confinement
region.
PLASMA HEATING
RF heating studies with fundamental ion cyclotron
resonance heating on minority deuterium ions predict
efficient heating with good coupling between the antenna
and the plasma [18]. Tritium ions can be heated with
second harmonic heating [19]. Antenna frequencies are
matched to cyclotron resonance conditions at a magnetic
field strength equal to half the maximum field strength,
corresponding to locations of sloshing ion density peaks.
The antennas for deuterium and tritium heating can be
located at opposite ends of the mirror machine. The RF
heating waves propagates from the strong field side
towards weaker field. Conversion between fast
magnetosonic wave and compressional Alfven wave
occurs at a conversion surface and resonant absorption
occurs at cyclotron harmonics.
Geometrically, the RF heating option has the
advantage that no holes (except at the longitudinal ends of
the confinement region) are introduced in the fission
mantle [18]. Shielding of the antennas as well as steady
state heating are possible with ICRH.
NEUTRON AND COOLING COMPUTATIONS
In Monte Carlo simulations for the neutrons [4, 5], the
geometry and materials in the fission mantle is designed to
have an initial neutron multiplicity of keff = 0.97. This
number is selected with the expectation that the reactor
would remain in a subcritical state even in “worst case
scenarios” [4, 5]. This has been confirmed by detailed
Monte Carlo simulations modeling of scenarios with loss
of coolants, void of coolants and partial replacement of
the lead-bismuth coolant by water (this could increase
fission production by the moderation of neutrons). A
connection of the coolant tubes in the buffer and reactor
core region is a mean to avoid a reactivity increase when
water is entering the coolant tubes. With this arrangement
the increase in keff is below 2% in all cases studied, which
suggests that a blanket design with keff = 0.97 initially
would retain the reactor in a subcritical state even for a
worst case accident [4, 5].
The buffer reduces the neutron load on the stainless
steel first wall. For the 1.5 GW thermal power case, the
200 dpa limit for the first wall is predicted to correspond
to more than 30 years, with 311 days of steady state
operation at fixed power each year. The fuel is slowly
burned out, resulting in a lowered keff. In the 1.5 GW
thermal case, keff decreases to about 0.95 in a one
year operation. The power amplification
multiplication at the beginning of the cycle is
PAF = 147 (with keff =0.97) and is reduced at the end
of the cycle by about 40% in a scenario where
control rods or burning absorbers are not used to
maintain the core at a constant keff. A constant power
output has in such a case to be maintained by
increasing the neutron intensity from the fusion
neutron source.
The blanket is designed for tritium reproduction
[4]. The computed tritium breeding ratio is around
1.8 in a one year power cycle (this overproduction of
tritium can easily be adjusted down to lower values).
Empty spatial locations within the blanket which
could be used to increase the neutron shielding.
Neutron heat load on the superconducting coils been
calculated, and an effective shielding of
superconductors and antennas can be made with
boronized layers.
The vertical orientation of the mirror device could
be favorable for self-circulation of the coolant, which
is a safety arrangement to remove decay heat [6]. At
full 1.5 GWth power production, pumping at a
moderate pumping power (less than 50 MW) is
predicted [2, 6].
SUMMARY
A power producing reactor has preferentially to
operate in steady state (for a year or longer).
Geometries with local neutron production seem well
suited for a steady state hybrid reactor, and a high
power amplification by fission is possible with
reactor safety demands satisfied. Sufficient space is
available between the vacuum chamber and the
magnetic coils to introduce a buffer (for first wall
protection against neutron bombardment), fission
fuel, neutron reflectors, coolant tubes, shielding,
tritium breeding zones and other necessary
components. Plasma heating in ion cyclotron range
of frequencies has been considered in the studies,
and a beneficial feature is that this choice of heating
does not split the fission reactor core into two
separate parts, as in Ref. 20. Monte Carlo
simulations predict that the reactor remains
subcritical in reactor safety events (loss and boiling
of coolants) with a tolerable load on the first wall
(the 200 dpa limit corresponds to more than 30 full
power years). Load associated with longitudinal
plasma loss could be taken care of with large
expanders beyond the confinement region.
Plasma stability is a threat for the efficiency of
the system. Large scale plasma activity is not
foreseen with an average minimum B field. A “semi-
poor” confinement is adequate in the hybrid case,
making the hybrid less vulnerable to small scale
plasma activity.
Biased potential endplates is in mirror machines
a mean to improve radial confinement. A recent
study [20] has shown the existence of a radial
invariant in the collsion free approximation, where
magnetic radial drift leakage (due to field errors or
ISSN 1562-6016. ВАНТ. 2015. №1(95) 7
other disturbances) could be cured by creating a slow drift
around the magnetic axis. In this way a radially bounded
motion could be arranged for all guiding centers when
collisions are neglected. The situation is more complex in
stellarators, where existence of nested flux surfaces in
practice is a necessary condition for radial confinement.
Magnetic drifts may still cause radial leakage, even in
regions with nested flux surfaces. However, recent studies
has shown that a weak radial electric field can restore
radial confinement for a majority of such particles where
the radial magnetic drift is a threat for their confinement.
The electron temperature is a critical parameter for
mirror machines. Means to achieve an electron
temperature in the range of 1 keV or more [3], which
could be sufficient for power production in a mirror
hybrid device, are addressed. Power production in the
hybrid reactor concepts are predicted with a fusion Q as
low as 0.15, which is one order smaller than predicted
critical Q factors for tokamak hybrids. Similar limits on
the Q factor is expected for the stellarator-mirror concept
[21].
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Fusion. 2014, v. 56, p. 094008.
Article received 25.12.2014
КОНЦЕПЦИИ СТАЦИОНАРНЫХ ЯДЕРНО-ТЕРМОЯДЕРНЫХ РЕАКТОРОВ НА ОСНОВЕ
СТЕЛЛАРАТОРА-ПРОБКОТРОНА И ПРОБКОТРОНА
O. Ågren, В.Е. Моисеенко, К. Ноак, С.В. Черницкий
Источники нейтронов и гибридные реакторы предоставляют возможность применения термоядерного
синтеза в не слишком отдаленном будущем. Стационарный режим работы без перерывов необходим для
таких устройств. В ответ на эту потребность наши исследования сосредоточены на концепциях, которые не
ограничиваются работой только в импульсном режиме. Особое внимание уделяется пробкотронным
устройствам и концепции стелларатора-пробкотрона, которые характеризуются локализованным
излучением нейтронов. Рассмотрены вопросы безопасности реактора, формы магнитных катушек, усиления
мощности за счет реакции деления, нагрева плазмы и роли радиального инварианта движения ионов,
который обеспечивает удержание ионов при их радиально колебательном движении в бесстолкновительном
приближении.
КОНЦЕПЦІЇ СТАЦІОНАРНИХ ЯДЕРНО-ТЕРМОЯДЕРНИХ РЕАКТОРІВ НА ОСНОВІ
СТЕЛАРАТОРА-ПРОБКОТРОНА І ПРОБКОТРОНА
O. Ågren, В.Є. Моісеєнко, К. Ноак, С.В. Черницький
Джерела нейтронів і гібридні реактори надають можливість застосування термоядерного синтезу в не
занадто віддаленому майбутньому. Стаціонарний режим роботи без перерв потрібний для таких пристроїв.
У відповідь на цю потребу наші дослідження зосереджені на концепціях, які не обмежуються роботою
тільки в імпульсному режимі. Особлива увага приділяється пробкотронним пристроям і концепції
стеларатора-пробкотрона, які характеризуються локалізованим випромінюванням нейтронів. Розглянуті
питання безпеки реактора, форми магнітних котушок, посилення потужності за рахунок реакції ділення,
нагріву плазми і ролі радіального інваріанту руху іонів, який забезпечує утримання іонів при їх радіально
коливальному русі в беззіштовхувальному наближенні.
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| id | nasplib_isofts_kiev_ua-123456789-82101 |
| institution | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| issn | 1562-6016 |
| language | English |
| last_indexed | 2025-11-30T11:28:11Z |
| publishDate | 2015 |
| publisher | Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| record_format | dspace |
| spelling | Ågren, O. Moiseenko, V.E. Noack, K. Chernitskiy, S.V. 2015-05-25T06:21:41Z 2015-05-25T06:21:41Z 2015 Steady-state fusion fission reactor concepts based on stellarator-mirror and mirror machines/ O. Ågren, V.E. Moiseenko, K. Noack, S.V. Chernitskiy // Вопросы атомной науки и техники. — 2015. — № 1. — С. 3-7. — Бібліогр.: 21 назв. — англ. 1562-6016 PACS: 52.65.Сс, 52.55.Hc, 28.50.Ft https://nasplib.isofts.kiev.ua/handle/123456789/82101 Neutron sources and hybrid reactors offer a possibility for application of fusion in a not too distant future. Steady-state operation on a time scale of a year without interruption is essential for such applications. In response to this need, our studies are focused on concepts which are not limited by pulsed operation. Special attention is put on mirror machines and a stellarator-mirror concept with localized neutron production. Reactor safety, magnetic coils, power amplification by fission, plasma heating, a radial constant of motion which provides a bounded radial motion in the collision free approximation are some of the issues addressed. Источники нейтронов и гибридные реакторы предоставляют возможность применения термоядерного синтеза в не слишком отдаленном будущем. Стационарный режим работы без перерывов необходим для таких устройств. В ответ на эту потребность наши исследования сосредоточены на концепциях, которые не ограничиваются работой только в импульсном режиме. Особое внимание уделяется пробкотронным устройствам и концепции стелларатора-пробкотрона, которые характеризуются локализованным излучением нейтронов. Рассмотрены вопросы безопасности реактора, формы магнитных катушек, усиления мощности за счет реакции деления, нагрева плазмы и роли радиального инварианта движения ионов, который обеспечивает удержание ионов при их радиально колебательном движении в бесстолкновительном приближении. Джерела нейтронів і гібридні реактори надають можливість застосування термоядерного синтезу в не занадто віддаленому майбутньому. Стаціонарний режим роботи без перерв потрібний для таких пристроїв. У відповідь на цю потребу наші дослідження зосереджені на концепціях, які не обмежуються роботою тільки в імпульсному режимі. Особлива увага приділяється пробкотронним пристроям і концепції стеларатора-пробкотрона, які характеризуються локалізованим випромінюванням нейтронів. Розглянуті питання безпеки реактора, форми магнітних котушок, посилення потужності за рахунок реакції ділення, нагріву плазми і ролі радіального інваріанту руху іонів, який забезпечує утримання іонів при їх радіально коливальному русі в беззіштовхувальному наближенні. en Національний науковий центр «Харківський фізико-технічний інститут» НАН України Вопросы атомной науки и техники Магнитное удержание Steady-state fusion fission reactor concepts based on stellarator-mirror and mirror machines Концепції стаціонарних ядерно-термоядерних реакторів на основі стеларатора-пробкотрона і пробкотрона Концепции стационарных ядерно-термоядерных реакторов на основе стелларатора-пробкотрона и пробкотрона Article published earlier |
| spellingShingle | Steady-state fusion fission reactor concepts based on stellarator-mirror and mirror machines Ågren, O. Moiseenko, V.E. Noack, K. Chernitskiy, S.V. Магнитное удержание |
| title | Steady-state fusion fission reactor concepts based on stellarator-mirror and mirror machines |
| title_alt | Концепції стаціонарних ядерно-термоядерних реакторів на основі стеларатора-пробкотрона і пробкотрона Концепции стационарных ядерно-термоядерных реакторов на основе стелларатора-пробкотрона и пробкотрона |
| title_full | Steady-state fusion fission reactor concepts based on stellarator-mirror and mirror machines |
| title_fullStr | Steady-state fusion fission reactor concepts based on stellarator-mirror and mirror machines |
| title_full_unstemmed | Steady-state fusion fission reactor concepts based on stellarator-mirror and mirror machines |
| title_short | Steady-state fusion fission reactor concepts based on stellarator-mirror and mirror machines |
| title_sort | steady-state fusion fission reactor concepts based on stellarator-mirror and mirror machines |
| topic | Магнитное удержание |
| topic_facet | Магнитное удержание |
| url | https://nasplib.isofts.kiev.ua/handle/123456789/82101 |
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