Minor actinides burning in a stellarator-mirror fusion-fission hybrid
The MCNPX Monte-Carlo code has been used to model a compact concept of a fusion-fission reactor based on a combined stellarator-mirror trap for transmutation transuranic elements from the spent nuclear fuel. Calculation results for fission rates for transuranic elements are presented. С использовани...
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| Опубліковано в: : | Вопросы атомной науки и техники |
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| Дата: | 2015 |
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Національний науковий центр «Харківський фізико-технічний інститут» НАН України
2015
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| Цитувати: | Minor actinides burning in a stellarator-mirror fusion-fission hybrid / S.V. Chernitskiy, V.E. Moiseenko, O. Ågren, K. Noack // Вопросы атомной науки и техники. — 2015. — № 1. — С. 20-23. — Бібліогр.: 14 назв. — англ. |
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Digital Library of Periodicals of National Academy of Sciences of Ukraine| _version_ | 1859745691922857984 |
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| author | Chernitskiy, S.V. Moiseenko, V.E. Ågren, O. Noack, K. |
| author_facet | Chernitskiy, S.V. Moiseenko, V.E. Ågren, O. Noack, K. |
| citation_txt | Minor actinides burning in a stellarator-mirror fusion-fission hybrid / S.V. Chernitskiy, V.E. Moiseenko, O. Ågren, K. Noack // Вопросы атомной науки и техники. — 2015. — № 1. — С. 20-23. — Бібліогр.: 14 назв. — англ. |
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| container_title | Вопросы атомной науки и техники |
| description | The MCNPX Monte-Carlo code has been used to model a compact concept of a fusion-fission reactor based on a combined stellarator-mirror trap for transmutation transuranic elements from the spent nuclear fuel. Calculation results for fission rates for transuranic elements are presented.
С использованием программы MCNPX разработана модель контролированного гибридного реактора небольших размеров на основе открытой ловушки для трансмутации трансурановых изотопов из отработавшего ядерного топлива. Представлены результаты расчетов скорости деления трансурановых элементов.
За допомогою програми MCNPX розроблена модель контрольованого гібридного ректора невеликих розмірів на основі відкритої пастки для трансмутації трансуранових ізотопів з відпрацьованого ядерного палива. Представлені результати розрахунків швидкості ділення трансуранових елементів.
|
| first_indexed | 2025-12-01T21:27:19Z |
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ISSN 1562-6016. ВАНТ. 2015. №1(95)
20 PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. 2015, № 1. Series: Plasma Physics (21), p. 20-23.
MINOR ACTINIDES BURNING IN A STELLARATOR-MIRROR
FUSION-FISSION HYBRID
S.V. Chernitskiy
1
, V.E. Moiseenko
2
, O. Ågren
3
, K. Noack
3
1
“Nuclear Fuel Cycle” Science and Technology Establishment NSC
‘‘Kharkov Institute of Physics and Technology”, Kharkov, Ukraine;
2
Institute of Plasma Physics of the NSC ‘‘Kharkov Institute of Physics and Technology”,
Kharkov, Ukraine;
3
Uppsala University, Ångström Laboratory, Uppsala, Sweden
The MCNPX Monte-Carlo code has been used to model a compact concept of a fusion-fission reactor based on a
combined stellarator-mirror trap for transmutation transuranic elements from the spent nuclear fuel. Calculation
results for fission rates for transuranic elements are presented.
PACS: 52.55.Hc
INTRODUCTION
Utilization of spent nuclear fuel is an actual global
problem. Storing it in geological nuclear waste
repositories is not a sustainable solution. Because of the
slow decrease of radioactivity, the repository term is
incredibly long, about 300.000 years [1]. The long-term
radiotoxicity of waste (Fig. 1) is clearly dominated by
actinides. An option for geological storage is separation
of transuranic elements and burning them in fast
reactors. The waste without transuranic content
becomes non-radioactive much faster.
Fig. 1.Time evolution of the potential radiotoxicity
(relative to uranium ore) of the two main components of
nuclear waste for PWR spent fuel
Fuel with transuranic elements could be burned in a
fast reactor, but has a deficit in delayed neutrons, which
decrease the reactor controllability [2, 3]. Fast reactors
with liquid metal coolant (for example Na) have a
positive void effect of reactivity, which is also a
drawback of the reactors from the point of view of
nuclear safety. Besides reducing the value of the
Doppler-effect at the fast reactors, unlike pressurized
water reactors (PWR), leading to deterioration of
nuclear safety in the case of accident situations, such as
an increase the temperature of the fuel in the reactor.
Thus, an attractive idea is the development of a
subcritical reactor, the main purpose of which will be a
safe burning of transuranic elements from the spent
nuclear fuel. The sub-critical reactors which are
controlled by an external neutron source are more
costly, but have certain advantages before critical
reactors. Together with efficient power production they
offer an improved controllability of the chain fission
reaction that boosts reactor safety.
STELLARATOR-MIRROR HYBRID
In Ref. 4 a stellarator-mirror hybrid reactor (Fig. 2)
is proposed. It consists of a magnetic trap for plasma
confinement in which fusion neutrons are generated and
a sub-critical fast reactor driven by these neutrons. The
magnetic trap is of a combined type: it is a toroidal
stellarator with an embedded magnetic mirror with
lower magnetic field.
Fig. 2. Sketch of the fission-fusion hybrid
The stellarator part provides confinement of warm
dense deuterium target plasma. Hot sloshing tritium ions
are confined at the mirror part of the device. At this part
the plasma column is straight. The hot minority tritium
ions are sustained in the plasma by the neutral beam
injection (NBI). The NBI is normal to the magnetic field
and targets plasma just near the fission mantle border.
The sloshing ions bounce inside the magnetic mirror
between the injection point and mirror point where the
magnetic field has the same value as the in injection
point. The toroidal plasma confinement in such a device
depends on whether the magnetic surfaces exist in it.
The study made in Ref. 5 shows that under certain
conditions the nested magnetic surfaces could be
created in a stellarator-mirror machine.
The embedded magnetic mirror is surrounded by a
cylindrically symmetrical fission mantle described in
Ref. 6. The calculations made in that paper indicate that
it is possible to achieve an appropriate criticality for the
mantle of compact size.
CALCULATION MODEL
The model is cylindrically symmetric and has a
horizontal axis (see Ref. 6). Its radial and axial structure
is shown in Fig. 3. The reactor has an axial opening that
ISSN 1562-6016. ВАНТ. 2015. №1(95) 21
contains vacuum chamber with D-T plasmas which
supplies the fusion neutrons.
The inner radius of the vacuum chamber is 0.5 m.
For the first wall a thickness of 3 cm was chosen. The
first wall is made of HT-9 steel [7].
The thickness was determined from the results of
critically calculations. The reactor core thickness of
27.8 cm was chosen to make the effective multiplication
factor keff≈0.95. The length of the core is 3 m. It has
axial reflectors on both sides. The radial reflector in the
model is a homogeneous mixture of HT-9 steel and
Li17Pb83 (20% enriched Li-6) with the volume
fractions 70 and 30%, respectively. This mixture is used
for tritium breeding: from the reaction
6
Li(n,α)T.
The shield contains a 60:40 vol.% mixture of the
stainless steel alloy S30467 type 304B7 [8] with water.
The steel contains 1.75 wt.% of natural boron. A shield
is used to reduce the neutron and gamma loads of the
stellarator-mirror magnetic coils needed for the plasma
confinement. The shield thickness is of 25 cm. All the
materials, as well as their temperatures, which are
included in the design were taken from Ref. 9.
The active zone of the reactor is represented in the
model as a homogenized mixture of fuel,
structure/cladding and coolant. HT-9 and the lead and
bismuth eutectic (LBE) were used as structure/cladding
and coolant materials, respectively.
The actual fuel material is the zirconium alloy
(TRU-10Zr) which consists of the transuranic elements,
as shown at the table 1, with 10 wt.% of zirconium [10].
The alloy has a mass density of 18.37 g/cm
3
. A core
volume of 4.3 m
3
contains about 5 tones of transuranic
elements.
The isotopic composition shown in Table 1 is
typical for the composition of the spent nuclear fuel
from PWRs after the removal of uranium. The
following volume fraction was used for the
homogenized fission blanket: fuel slug material – 0.14,
structure/cladding – 0.103, coolant – 0.695. In this
study, a specific fuel form was not considered. The LBE
was assumed to be a mixture of 44.5 wt.% lead and
55.5 wt.% bismuth. The following material has been
used for the axial reflectors: a homogeneous mixture of
HT-9 steel and LBE-coolant with the volume fractions
70 and 30 %, respectively.
The total length of the main part of the model is
4 m. Since the fusion neutron generation zone extends
slightly beyond the fission reactor core, as shown in
Fig. 3, and the fission neutrons also leak out here
through the axial opening, there is a need to prevent
leakage of these neutrons. To arrange that, this part of
the plasma column is surrounded by a vessel filled with
borated water [11].
The concentration of boron in the water was taken
10 g/kg. The isotopic content is B10 – 20% and B11 –
80%. The part with borated water has a length of 2.5 m at
both sides of the main part and a thickness is of 27 cm.
Fig. 4. Scheme of the reactor part of the fusion
-fission hybrid
At the right side of the reactor, openings are made
to provide access to the plasma for the neutral beam
(Fig. 4, inlet hole for neutral beam injection).
In the calculation model, a D-T fusion neutron
source was used. The emission density was distributed
within a number of cylindrical volumes of radius 10 cm
and with a length of 4 m. At every source point, the
fusion neutrons were emitted with a fixed kinetic energy
of 14.1 MeV and isotropic velocity distribution.
Fig. 3. Radial and axial structures of the mirror based fusion-fission hybrid model
The relative intensity distribution along the length
of the neutron source used in the MCNPX model is
taken from Ref. 12. The total fusion power is 17 MW.
RESULTS OF CALCULATIONS
The MCNPX code [13] has been used to model the
neutron transport of the stellarator-mirror fusion-fission
reactor.
For the calculation for described above model, the
average fission energy deposited in the core per incident
source neutron is 1200±1% MeV. This high number
resulted from closeness to unity of the neutron
multiplication factor. With neutron generation intensity
6∙10
18
neutrons per second, the fission power is
Pfis≈1100 MW which corresponds to a power
22 ISSN 1562-6016. ВАНТ. 2015. №1(95)
multiplication factor, the ratio of power released to fusion
power, of 65.
Besides, a calculation with sodium coolant that may
be used instead of LBE coolant is performed. For
comparison, calculation results for the total energy,
deposited in the core per one source neutron, with LBE
and sodium coolants are presented at the Table 2.
Table 2. The fission energy, deposited in the core per
one source neutron
Coolant LBE Coolant Na
1200 MeV 1160 MeV
It should be noted that in the model with usage of
sodium coolant, the volume of the active zone was
significantly increased in the radial direction in order to
provide keff ~0.95. For this case, a core volume of 15 m
3
contains about 18 tones of transuranic elements. The
Table 2 prompts that total power of the installation
remains almost the same.
The spectrum of the neutron flux is important for
burnup and transmutation of the fuel. Fig. 5 shows the
energy group fluxes (neutron flux integrated over
energy intervals) per one fusion neutron averaged over
the active zone of the reactor. The statistical errors are
around 1% for all the results presented below.
Fig. 5. Averaged energy group fluxes
Fig. 5 also indicates that fusion neutrons in the core
are in minority, while the major part of the spectrum
represents the fission spectrum. Furthermore, in the
spectrum of neutrons with the sodium coolant, a
substantial portion of low-energy neutrons is present.
Fission is the ultimate nuclear reaction concerning
the incineration of long-lived fissionable fuel isotopes.
Thus, it is of particular interest to know which fission
rate has each fissionable isotope. The MCNPX is
calculating a reaction rate following the formula:
R = N∙∫φ(E)σ(E)dE ,
where φ(E) is the energy-dependent fluence per one
source neutron (cm
-2
); σ(E) is the energy-dependent
microscopic reaction cross section (barn); N is the
atomic density of material (atoms∙barn
-1
∙cm
-1
).
Fig. 6. Fission rates of fuel isotopes per fusion neutron
and per nucleus
The diagram of Fig. 6 displays the calculated
fission reaction rates for isotopes contained in the fuel
of the present fusion-fission hybrid. The represented
quantity is the average number of fission reactions
produced per fusion source neutron and per nucleus
considered. The diagram indicates that the well
fissionable isotopes
235
U,
239
Pu,
241
Pu,
242m
Am,
243
Cm
and
245
Cm have the highest fission rates, whereas the
hardly fissionable isotopes have fission rates about one
order of magnitude less.
The diagram of Fig. 7 illustrates the calculated
average number of fission reactions produced per one
fusion neutron given concentration of the TRU in the
fuel.
Fig. 7. Fission rates of fuel isotopes per fusion neutron
The diagram demonstrates that the burning of
transuranics per cm
3
much better in case coolant LBE
because the density of the material per unit volume
varies for different coolants.
Calculation results for the burnup of the TRU are
presented below. In the calculations for each isotope
accounts a decrease in its amount due to the reactions of
fission and neutron capture, as well as an increase due
to the neutron capture reaction and beta decay of the
neighbouring isotopes.
1 1
( )
( ) ( ) ( ) ( )
( ) ( ).
A
A A A AZ
f Z Z c Z Z
A A
c Z Z
dN M
M N M M N M
dt
M N M
Table 3. Burning TRU per year
Isotope
Burnup
coolant LBE coolant Na
U-235 -17 % -6 %
U-236 +3.5 % +2 %
U-238 -2.3 % -2 %
Pu-239 -14.3 % -6 %
Pu-240 -1.5 % +3 %
Pu-241 -3.2 % +4.4 %
Pu-242 -3.2 % -0.5 %
Np-237 -11 % -5.3 %
Am-241 -17 % -8 %
Am-242m +100 % +100 %
Am-243 -15 % -7.7 %
Cm-243 -28 % -12.7 %
Cm-244 -12 % -4.3 %
Cm-245 +40 % +25 %
Cm-246 +29 % +13.7 %
As seen from the results, of the Table 3 rates of
burning of minor actinides are suitably high. Increase
the amount of some isotopes occurs only for those ones
which amount is small.
The Table 4 shows the amount of transuranic, which
burns throughout the year for the present fusion-fission
ISSN 1562-6016. ВАНТ. 2015. №1(95) 23
hybrids. This value is compared with the amount of
TRU produced at the one light water reactor (LWR) per
year [14, 15].
Table 4. Composition and quantity of the TRU burning
at the hybrid reactor per year
Element
The amount of
TRU
established at
the one LWR
reactor per
year
Burnup of the
TRU at the
hybrid reactor
with coolant
LBE
Burnup of the
TRU at the
hybrid reactor
with coolant
Na
Uranium 20.000 kg - -
Neptunium 12 kg 13 kg 22 kg
Plutonium 205 kg 220 kg 231 kg
Americium 20 kg 21 kg 23 kg
Curium 0.4 kg 0.16 kg 0.13 kg
One can see that the burnup of the TRU for the
hybrid reactor with different coolants almost the same,
and also it is close to the amount of TRU produced in
one LWR reactor.
CONCLUSIONS
The results of the calculations that were carried out with
the Monte Carlo code MCNPX can be summarized as
follows:
1. The neutron spectrums in the blanket with
using two types of coolant are calculated.
2. Calculation results for the fission reaction rates
for transuranic elements are presented.
3. Burnup of the isotopes contained in the fuel of
the present fusion-fission hybrid are shown.
The calculations demonstrate that analysed version of
the subcritical reactor can provide complete transmutation
of TRU. The results of calculations also allow one to make
estimates for necessary fleet of such reactors needed to
empty nuclear repositories in given term.
One of the opportunities to provide sustainable
usage of nuclear energy is simultaneous operation of
LWR and hybrids. However in this scheme, each LWR
needs one hybrid reactor for transmutation its TRU.
ACKNOWLEDGEMENT
This work is supported in part by a grant from the
Swedish Institute.
REFERENCES
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Moscow, 2011.
2. V. Puchkov, E. Puchkova. Kinetics features of fast
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reactor // Fusion Science and Technology. 2002, v. 41,
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11. M.A. Filand, E.I. Semenova. Properties of rare
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13. For the U.S. DEPARTMENT OF ENERGY, Monte
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13. Y.V. Rudychev, M.A. Khazhmuradov, R.P. Slabos-
pitskij. Physical ground for radioactive waste
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Problems of Atomic Science and Technology. Series
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Article received 22.11.2014
ВЫГОРАНИЕ МИНОРНЫХ АКТИНИДОВ В ГИБРИДНОМ РЕАКТОРЕ
НА ОСНОВЕ СТЕЛЛАРАТОРА И ОТКРЫТОЙ ЛОВУШКИ
С.В. Черницкий, В.Е. Моисеенко, O. Ågren, К. Ноак
С использованием программы MCNPX разработана модель контролированного гибридного реактора
небольших размеров на основе открытой ловушки для трансмутации трансурановых изотопов из
отработавшего ядерного топлива. Представлены результаты расчетов скорости деления трансурановых
элементов.
ВИГОРАННЯ МІНОРНИХ АКТИНІДІВ У ГІБРИДНОМУ РЕАКТОРІ
НА ОСНОВІ СТЕЛАРАТОРА ТА ВІДКРИТОЇ ПАСТКИ
С.В. Черницький, В.Є. Моісеєнко, O. Ågren, К. Ноак
За допомогою програми MCNPX розроблена модель контрольованого гібридного ректора невеликих
розмірів на основі відкритої пастки для трансмутації трансуранових ізотопів з відпрацьованого ядерного
палива. Представлені результати розрахунків швидкості ділення трансуранових елементів.
http://www.ms.ornl.gov/programs/fusionmtlspdf/june1999/hashimoto1.pdf
http://www.ms.ornl.gov/programs/fusionmtlspdf/june1999/hashimoto1.pdf
http://vant.kipt.kharkov.ua/CONTENTS/CONTENTS_2004_4rus.html
http://vant.kipt.kharkov.ua/CONTENTS/CONTENTS_2004_4rus.html
|
| id | nasplib_isofts_kiev_ua-123456789-82102 |
| institution | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| issn | 1562-6016 |
| language | English |
| last_indexed | 2025-12-01T21:27:19Z |
| publishDate | 2015 |
| publisher | Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| record_format | dspace |
| spelling | Chernitskiy, S.V. Moiseenko, V.E. Ågren, O. Noack, K. 2015-05-25T06:23:41Z 2015-05-25T06:23:41Z 2015 Minor actinides burning in a stellarator-mirror fusion-fission hybrid / S.V. Chernitskiy, V.E. Moiseenko, O. Ågren, K. Noack // Вопросы атомной науки и техники. — 2015. — № 1. — С. 20-23. — Бібліогр.: 14 назв. — англ. 1562-6016 PACS: 52.55.Hc https://nasplib.isofts.kiev.ua/handle/123456789/82102 The MCNPX Monte-Carlo code has been used to model a compact concept of a fusion-fission reactor based on a combined stellarator-mirror trap for transmutation transuranic elements from the spent nuclear fuel. Calculation results for fission rates for transuranic elements are presented. С использованием программы MCNPX разработана модель контролированного гибридного реактора небольших размеров на основе открытой ловушки для трансмутации трансурановых изотопов из отработавшего ядерного топлива. Представлены результаты расчетов скорости деления трансурановых элементов. За допомогою програми MCNPX розроблена модель контрольованого гібридного ректора невеликих розмірів на основі відкритої пастки для трансмутації трансуранових ізотопів з відпрацьованого ядерного палива. Представлені результати розрахунків швидкості ділення трансуранових елементів. This work is supported in part by a grant from the Swedish Institute en Національний науковий центр «Харківський фізико-технічний інститут» НАН України Вопросы атомной науки и техники Магнитное удержание Minor actinides burning in a stellarator-mirror fusion-fission hybrid Выгорание минорных актинидов в гибридном реакторе на основе стелларатора и открытой ловушки Вигорання мінорних актинідів у гібридному реакторі на основі стеларатора та відкритої пастки Article published earlier |
| spellingShingle | Minor actinides burning in a stellarator-mirror fusion-fission hybrid Chernitskiy, S.V. Moiseenko, V.E. Ågren, O. Noack, K. Магнитное удержание |
| title | Minor actinides burning in a stellarator-mirror fusion-fission hybrid |
| title_alt | Выгорание минорных актинидов в гибридном реакторе на основе стелларатора и открытой ловушки Вигорання мінорних актинідів у гібридному реакторі на основі стеларатора та відкритої пастки |
| title_full | Minor actinides burning in a stellarator-mirror fusion-fission hybrid |
| title_fullStr | Minor actinides burning in a stellarator-mirror fusion-fission hybrid |
| title_full_unstemmed | Minor actinides burning in a stellarator-mirror fusion-fission hybrid |
| title_short | Minor actinides burning in a stellarator-mirror fusion-fission hybrid |
| title_sort | minor actinides burning in a stellarator-mirror fusion-fission hybrid |
| topic | Магнитное удержание |
| topic_facet | Магнитное удержание |
| url | https://nasplib.isofts.kiev.ua/handle/123456789/82102 |
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