Investigation of geometry and fuel composition in two-zone subcritical research reactor for nuclear waste transmutation
The investigations directed to optimization of fuel compositions for two-zone subcritical reactor is considered in present paper. The study of two-zone subcritical reactor with heterogeneous fuel regard to geometrical, material and economical characteristics was carried out within the scope of thi...
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| Опубліковано в: : | Вопросы атомной науки и техники |
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| Дата: | 2018 |
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Національний науковий центр «Харківський фізико-технічний інститут» НАН України
2018
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| Цитувати: | Investigation of geometry and fuel composition in two-zone subcritical research reactor for nuclear waste transmutation / D.O. Sheliahovskyi, V.I. Gulik, A.V. Nosovskyi // Вопросы атомной науки и техники. — 2018. — № 2. — С. 50-56. — Бібліогр.: 22 назв. — англ. |
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Digital Library of Periodicals of National Academy of Sciences of Ukraine| _version_ | 1859778467041640448 |
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| author | Sheliahovskyi, D.O. Gulik, V.I. Nosovskyi, A.V |
| author_facet | Sheliahovskyi, D.O. Gulik, V.I. Nosovskyi, A.V |
| citation_txt | Investigation of geometry and fuel composition in two-zone subcritical research reactor for nuclear waste transmutation / D.O. Sheliahovskyi, V.I. Gulik, A.V. Nosovskyi // Вопросы атомной науки и техники. — 2018. — № 2. — С. 50-56. — Бібліогр.: 22 назв. — англ. |
| collection | DSpace DC |
| container_title | Вопросы атомной науки и техники |
| description | The investigations directed to optimization of fuel compositions for two-zone subcritical reactor is considered in
present paper. The study of two-zone subcritical reactor with heterogeneous fuel regard to geometrical, material and
economical characteristics was carried out within the scope of this paper. The calculations of transmutation
characteristics for main isotopes regard to radioactive waste from conventional nuclear reactors was carried out. There
is a possibility for selection of material and geometrical characteristics of two-zone subcritical system in such a way as
to satisfy the objectives for development of subcritical reactor in relation to the magnitude of the neutron flux, the
transmutation parameters and the cost of system.
Представлені результати досліджень, спрямованих на оптимізацію паливного складу двозонного
підкритичного ядерного реактора. В рамках даної роботи були виконані дослідження двозонного
підкритичного реактора з гетерогенним складом палива відносно геометричних, матеріальних і економічних
параметрів розглянутої системи. Також було виконано розрахунок трансмутаційних характеристик системи
для основних ізотопів, які відносяться до проблемних елементів радіоактивних відходів діючих ядерних
реакторів. Було показано, що можна підібрати матеріальні і геометричні характеристики двозонної
підкритичній системи таким чином, щоб це задовольняло цілям створення підкритичного реактора щодо
величини потоку нейтронів, трансмутаційних параметрів і вартості системи.
Представлены результаты исследований, направленных на оптимизацию топливного состава
двухзонного подкритического ядерного реактора. В рамках данной работы были выполнены исследования
двухзонного подкритического реактора с гетерогенным составом топлива в отношении геометрических,
материальных и экономических параметров рассмотренной системы. Также был выполнен расчет
трансмутационных характеристик системы для основных изотопов, которые относятся к проблемным
элементам радиоактивных отходов действующих ядерных реакторов. Было показано, что можно подобрать
материальные и геометрические характеристики двухзонной подкритической системы таким образом, чтобы
это удовлетворяло целям создания подкритического реактора в отношении величины потока нейтронов,
трансмутационных параметров и стоимости системы.
|
| first_indexed | 2025-12-02T09:26:03Z |
| format | Article |
| fulltext |
ISSN 1562-6016. PASТ. 2018. №2(114), p. 50-56.
UDC 621.384.6
INVESTIGATION OF GEOMETRY AND FUEL COMPOSITION
IN TWO-ZONE SUBCRITICAL RESEARCH REACTOR
FOR NUCLEAR WASTE TRANSMUTATION
D.O. Sheliahovskyi, V.I. Gulik, A.V. Nosovskyi
Institute for Safety Problems of Nuclear Power Plants, Kyiv, Ukraine
E-mail: volodymyr.gulik@gmail.com
The investigations directed to optimization of fuel compositions for two-zone subcritical reactor is considered in
present paper. The study of two-zone subcritical reactor with heterogeneous fuel regard to geometrical, material and
economical characteristics was carried out within the scope of this paper. The calculations of transmutation
characteristics for main isotopes regard to radioactive waste from conventional nuclear reactors was carried out. There
is a possibility for selection of material and geometrical characteristics of two-zone subcritical system in such a way as
to satisfy the objectives for development of subcritical reactor in relation to the magnitude of the neutron flux, the
transmutation parameters and the cost of system.
INTRODUCTION
Further progress of nuclear energy in the world is
impossible without the development of new types of
research reactors, otherwise it is impossible to obtain
new experimental data for benchmark calculations,
verification of new software codes, etc.
One of the greatest challenges for nuclear energy is
highly radioactive waste generated during irradiation in
nuclear reactors. Most of the radioactive hazard from
irradiated nuclear fuel originates from only a few
chemical elements: plutonium, neptunium, americium,
curium and some long-lived fission products such as
iodine and technetium. These radioactive by-products,
although present at very low concentrations in the waste
fuel. As such, it requires isolation from environment in
stable deep geological formations for long periods of
time. Partitioning and transmutation (P&T) [1]
technology is considered as an instrument of reducing
the burden on a geological disposal. As plutonium and
the minor actinides (MA) are mainly responsible for the
long-term radiotoxicity, when these nuclides are first
removed from the irradiated fuel (partitioning) and then
fragmented by fission (transmutation), the remaining
waste loses most of its long-term radiotoxicity.
Accelerator driven systems (ADS) are advanced
nuclear systems, which are particularly suitable for
transmutation objectives. Such a nuclear reactor may be
employed to address several missions, for example
transmutation and generate electricity. ADS presents
several benefits: more flexible with respect to fuel
composition and potentially raised safety.
As the issue of spent fuel management is one of the
most important of the future nuclear power development
in the world, the study of transmutation possibilities
also relevant. There are many international projects in
this way, for example: MYRRHA [2], YALINA [3],
SAD etc., and Ukraine is no exception. We have already
built a subcritical system with an electron accelerator in
Kharkiv [4], and in the nearly future, it is planned to be
launched.
In this work, the authors’ main focus on
investigation of two-zone subcritical reactor driven by
high-intensity neutron generator.
1. MODELING SCHEME
AND CALCULATION METHODS
The presented subcritical system has two zones with
different neutron spectrum. A graphite moderator was
added to arrange the thermal neutron spectrum in the
outer zone. The scheme with light water moderator and
coolant is used, was not considered due to the risk of
light water getting into the inner zone during an
emergency and a significant splash of reactivity, as a
result. Helium was selected to be a coolant in the
internal and external zones [5].
The geometric and material characteristics of the
WWER-1000 reactor fuel rods were used in the fuel cell
model development for the subcritical reactor both
zones. The fuel in fuel cells is uranium dioxide at
different uranium-235 enrichment: System I (in the
internal enrichment zone – 10%, in the external
enrichment zone – 5%); System II (in the internal
enrichment zone – 15%, in the external enrichment zone
– 3%). The fuel density is 10.96 g/cm
3
, the fuel rod’s
shell is zirconium+1% of niobium, the fuel cell diameter
is 0.786 cm, the fuel rod’s shell diameter is 0.91 cm, the
fuel rods step in the inner zone is 1.275 cm. The fuel rod
placement square grid was selected for the subcritical
reactor both zones. The uranium dioxide enrichment in
the inner zone at the level of 10…15% was selected
based on the IAEA recommendations on reducing the
uranium-235 enrichment level in the subcritical research
reactors projects [6].
Fuel rods in the outer zone are located for the step of
5 cm. There is the space of the helium coolant to
dissipate heat, which is equivalent to the space in the
inner zone with the fuel rods step of 1.275 cm, around
each fuel rod.
The Monte-Carlo Serpent 2.1.26 code was used for
the neutron modeling in the calculations described
below [7]. This code is used successfully both for the
traditional nuclear reactors calculation and innovative
reactors [8–11] and for other applications [12, 13]. The
ENDF/B-VII library has been used as the evaluated
nuclear data library for all presented calculations [14].
mailto:volodymyr.gulik@gmail.com
2. SERPENT MODELING RESULTS
2.1. NEUTRON AND ECONOMIC PARAMETERS
CALCULATION OF SYSTEM WITH
HETEROGENEOUS FUEL COMPOSITION
The first step in the subcritical systems with
heterogeneous fuel composition study was to model the
change in the internal zone volume with fixed fuel
composition of both zones (for Systems I and II) and with
a fuel rod in the external zone fixed step of 5 cm. The
cross section of the subcritical reactor typical two-zone
model designed by Serpent code is shown in Fig. 1. Fig. 2
shows the “mesh” image of the subcritical reactor both
zones cross-section. As indicated in the Serpent code
description concerning the “mesh” images: “... the color
scheme is divided into “hot” shades of red and yellow,
representing the relative divisions power in the system,
and “cold” shades of blue, representing the relative heat
flux (the flow below 0.625 eV)”. Presented Figs. 1 and 2
belong to System I with the inner zone radius of 10.5 cm.
Fig. 1. A subcritical reactor typical model scheme
(cross-section)
Fig. 2. Mesh image of the subcritical reactor
(cross-section)
System I was modeled to change the inner zone radius
(and consequently the inner zone volume) in the range
from 10.5 to 43.5 cm, and System II was modeled to
change the inner zone radius in the range from 10.5 to
50.5 cm. The neutron fluxes normalized to one neutron of
an external source for internal and external zones and for
the entire subcritical system were counted. The main
Serpent modeling neutron, geometric and economic
characteristics for System I are presented in Tabl. 1, for
System II – in Tabl. 2. The main modeling parameters
were similar to those described in the previous article
(homogeneous model calculation) [19] in the “1.3
Modeling scheme” section and selected on the basis of
the author’s previous works [15–20].
The designations in Tables 1 and 2 include the
following values: Rint – the inner zone radius, cm;
Vext /Vint – ratio of external and internal zones volumes;
Fint – the neutron flux in the inner zone in relation to an
external source one neutron; Fext – the neutron flux in the
external zone in relation to an external source one
neutron; Fsum – the total neutron flux in the entire
subcritical system in relation to an external source one
neutron; Cint – estimated fuel cost in the inner zone, mln
Euro; Cext – estimated fuel cost in the external zone, mln
Euro; Csum – estimated fuel cost in the entire subcritical
system, mln Euro. The fuel cost estimate was based on
the current point price of uranium dioxide plus the
uranium-235 enrichment cost.
Table 1
The Serpent modeling of a two-zone subcritical model with heterogeneous fuel composition results (System І)
Rint, cm Vext/Vint Fint Fext Fsum
Cint,
mln Euro
Cext,
mln Euro
Csum,
mln Euro
1 2 3 4 5 6 7 8
10.50 49.51 7.01 221.03 228.03 0.35 0.54 0.89
11.50 40.71 8.32 218.76 227.08 0.43 0.54 0.97
12.50 34.24 9.74 216.42 226.15 0.52 0.55 1.07
13.50 29.34 11.06 215.67 226.73 0.62 0.56 1.18
14.50 25.26 12.68 213.25 225.93 0.73 0.57 1.29
15.50 22.18 14.19 210.38 224.57 0.85 0.58 1.42
16.50 19.60 15.61 208.51 224.11 0.97 0.59 1.56
17.50 17.51 17.04 206.75 223.78 1.11 0.60 1.70
18.50 15.85 18.55 204.87 223.42 1.26 0.61 1.87
1 2 3 4 5 6 7 8
19.50 14.35 20.20 203.06 223.26 1.41 0.62 2.03
20.50 13.02 21.84 200.63 222.47 1.57 0.63 2.21
21.50 11.91 23.52 199.18 222.69 1.75 0.64 2.39
22.50 11.04 24.75 198.33 223.08 1.94 0.66 2.60
23.50 10.13 26.65 195.47 222.12 2.14 0.67 2.80
24.50 9.40 28.29 193.10 221.39 2.35 0.68 3.03
25.50 8.75 29.99 191.47 221.45 2.57 0.69 3.26
26.50 8.18 31.37 189.41 220.77 2.80 0.71 3.51
27.50 7.66 33.13 188.31 221.44 3.05 0.72 3.77
28.50 7.19 34.90 186.80 221.70 3.31 0.73 4.04
29.50 6.77 36.33 184.97 221.30 3.58 0.75 4.32
30.50 6.39 38.16 182.24 220.40 3.86 0.76 4.62
31.50 6.04 39.79 180.86 220.64 4.16 0.77 4.93
32.50 5.73 41.49 179.14 220.63 4.47 0.79 5.26
33.50 5.44 43.29 177.35 220.64 4.79 0.80 5.59
34.50 5.15 45.06 175.11 220.17 5.12 0.81 5.93
35.50 4.89 46.86 173.02 219.88 5.46 0.82 6.29
36.50 4.66 48.69 171.55 220.23 5.83 0.83 6.66
37.50 4.45 50.34 170.29 220.62 6.21 0.85 7.06
38.50 4.27 51.59 168.63 220.21 6.61 0.87 7.47
39.50 4.08 53.56 166.02 219.58 7.01 0.88 7.89
40.50 3.91 55.45 164.29 219.74 7.43 0.89 8.33
41.50 3.74 57.30 162.59 219.89 7.87 0.91 8.78
42.50 3.62 58.55 162.27 220.82 8.35 0.93 9.28
43.50 3.47 60.65 159.76 220.41 8.80 0.94 9.74
It can seen from Tabl. 1 that with increasing the inner
zone volume, the neutron flux in the inner zone increases
significantly (by almost 9 times), and the neutron flux in
the outer zone decreases by 40%, while the total neutron
flux in both zones remains almost the same. During the
economic characteristics analysis the fuel cost in the inner
zone is seen to increase by about 25 times, the fuel cost in
the external zone – by 43% and the fuel cost of the whole
subcritical system – by almost 11 times. From these
results, we can conclude that in order to create favorable
conditions for investigating the transmutation of minor
actinides in the inner zone rapid spectrum, it is necessary
to increase the more enriched fuel volume significantly
and as a consequence, the cost of the entire subcritical
system increases significantly.
It can be seen from Tabl. 2 that using more enriched
fuel in the inner zone allows to get higher neutron fluxes
in the thermal zone, but at the same time the cost of the
entire subcritical system increases due to more expensive
enrichment to 15% by uranium-235. Using less enriched
fuel in the thermal zone allows to increase the thermal
zone size but then the cost of fuel in the thermal zone
increases.
Table 2
The Serpent modeling of a two-zone subcritical model with heterogeneous fuel composition results (System ІI)
Rint, сm Vext/Vint Fint Fext Fsum
Cint,
mln Euro
Cext,
mln Euro
Csum,
mln Euro
1 2 3 4 5 6 7 8
10.50 73.42 6.82 265.36 272.18 0.55 0.73 1.28
11.50 59.76 8.28 262.39 270.67 0.67 0.73 1.40
12.50 49.48 9.71 258.73 268.44 0.80 0.73 1.53
13.50 41.73 11.23 255.58 266.81 0.94 0.72 1.67
14.50 35.69 12.84 251.93 264.77 1.10 0.72 1.82
15.50 30.86 14.70 248.46 263.15 1.27 0.72 1.98
16.50 26.93 16.37 244.30 260.67 1.44 0.71 2.16
17.50 23.58 18.56 240.23 258.79 1.63 0.71 2.34
18.50 20.90 20.50 236.54 257.03 1.83 0.70 2.53
19.50 18.72 22.25 233.07 255.32 2.04 0.70 2.75
20.50 16.78 24.42 229.14 253.55 2.27 0.70 2.97
21.50 15.12 26.45 225.10 251.55 2.50 0.69 3.19
22.50 13.66 28.73 220.86 249.59 2.74 0.69 3.43
23.50 12.42 31.02 216.96 247.98 3.00 0.68 3.68
24.50 11.32 33.27 212.73 246.00 3.27 0.68 3.94
25.50 10.35 35.59 208.38 243.97 3.54 0.67 4.22
26.50 9.49 38.15 203.71 241.85 3.83 0.67 4.50
1 2 3 4 5 6 7 8
27.50 8.73 40.24 200.16 240.40 4.13 0.66 4.79
28.50 8.07 42.67 196.24 238.92 4.45 0.66 5.11
29.50 7.48 45.07 191.80 236.87 4.78 0.66 5.43
30.50 6.92 47.68 187.48 235.16 5.11 0.65 5.76
31.50 6.42 49.84 183.48 233.32 5.46 0.64 6.10
32.50 5.98 52.62 179.25 231.87 5.82 0.64 6.46
33.50 5.56 55.18 174.71 229.88 6.19 0.63 6.82
34.50 5.19 57.34 171.01 228.34 6.57 0.63 7.20
35.50 4.84 59.99 166.38 226.37 6.96 0.62 7.58
36.50 4.53 62.62 162.66 225.28 7.37 0.61 7.99
37.50 4.27 64.83 159.30 224.13 7.81 0.61 8.42
38.50 4.01 67.45 155.11 222.56 8.25 0.61 8.85
39.50 3.75 69.99 151.06 221.05 8.68 0.60 9.28
40.50 3.53 72.28 147.34 219.62 9.14 0.59 9.73
41.50 3.33 75.05 143.17 218.22 9.62 0.59 10.21
42.50 3.12 77.61 139.28 216.89 10.09 0.58 10.67
43.50 2.95 79.91 135.34 215.25 10.59 0.57 11.17
44.50 2.78 82.60 131.42 214.02 11.10 0.57 11.67
45.50 2.63 84.88 128.01 212.90 11.64 0.56 12.20
46.50 2.47 87.35 124.14 211.49 12.16 0.55 12.71
47.50 2.33 90.06 120.39 210.45 12.70 0.54 13.25
48.50 2.21 92.23 116.90 209.13 13.28 0.54 13.82
49.50 2.09 94.50 113.20 207.71 13.85 0.53 14.38
50.50 1.99 96.71 110.26 206.97 14.47 0.53 14.99
2.2. CALCULATION OF A SYSTEM WITH A
HETEROGENEOUS FUEL COMPOSITION
TRANSMUTATIONAL CHARACTERISTICS
Since one of the main presented subcritical reactor
assignments is the radioactive waste transmutation study,
a number of studies have been carried out to determine
the main transmutation characteristics. Such Serpent
simulations results are presented in Tabl. 3 for System I
and Tabl. 4 for System II. The Np-237 and Am-243
radioactive isotopes were selected from the minor
actinides group and I-129 and Tc-99 were selected from
the long-lived fission products group for the subcritical
system transmutation characteristics study [21].
Table 3
Transmutation characteristics of a two-zone subcritical model with heterogeneous fuel composition (System І)
Rint, сm
σf
Np-237
,
barn
σf
Am-243
,
barn
σc
Np-237
,
barn
σc
Am-243
,
barn
α
Np-237
α
Am-243
σc
I-129
,
barn
σc
Tc-99
,
barn
1 2 3 4 5 6 7 8 9
10.50 0.4992 0.3654 12.3855 24.9477 24.81 68.28 5.2583 15.7608
11.50 0.4945 0.3566 11.3526 23.0604 22.96 64.66 5.2351 15.7291
12.50 0.4900 0.3502 10.9041 22.0777 22.25 63.04 5.2259 15.7262
13.50 0.4833 0.3427 10.2751 20.7755 21.26 60.62 5.2176 15.7207
14.50 0.4826 0.3401 9.6706 19.5964 20.04 57.62 5.2081 15.6873
15.50 0.4749 0.3302 8.9985 18.2190 18.95 55.18 5.1764 15.7013
16.50 0.4700 0.3246 8.4686 17.2603 18.02 53.18 5.1607 15.6795
17.50 0.4692 0.3227 8.2013 16.4375 17.48 50.94 5.1597 15.6779
18.50 0.4656 0.3185 7.9632 16.5041 17.10 51.81 5.1434 15.6900
19.50 0.4614 0.3136 7.5949 15.3214 16.46 48.86 5.1328 15.6732
20.50 0.4587 0.3101 7.2880 14.9243 15.89 48.12 5.1162 15.6655
21.50 0.4552 0.3059 6.8847 14.1817 15.12 46.36 5.1140 15.6528
22.50 0.4506 0.3011 6.7580 13.6573 15.00 45.36 5.1157 15.6690
23.50 0.4472 0.2974 6.6177 12.9505 14.80 43.55 5.0968 15.6560
24.50 0.4448 0.2950 6.3249 12.7432 14.22 43.19 5.0815 15.6372
25.50 0.4416 0.2914 6.0863 12.1703 13.78 41.76 5.0736 15.6698
26.50 0.4379 0.2876 5.8645 11.8307 13.39 41.14 5.0558 15.6278
27.50 0.4341 0.2844 5.8405 11.6339 13.45 40.90 5.0628 15.6506
28.50 0.4332 0.2833 5.6817 11.3048 13.11 39.91 5.0560 15.6309
29.50 0.4278 0.2784 5.5146 10.9821 12.89 39.44 5.0520 15.6327
30.50 0.4269 0.2767 5.2857 10.3033 12.38 37.24 5.0328 15.6043
31.50 0.4237 0.2739 5.1828 10.1327 12.23 36.99 5.0279 15.5983
1 2 3 4 5 6 7 8 9
32.50 0.4221 0.2724 5.1477 10.1250 12.19 37.17 5.0208 15.6141
33.50 0.4200 0.2703 5.0033 9.8747 11.91 36.53 5.0146 15.6037
34.50 0.4180 0.2682 4.8613 9.3366 11.63 34.81 5.0075 15.5863
35.50 0.4158 0.2661 4.7311 8.9581 11.38 33.67 4.9905 15.5917
36.50 0.4135 0.2642 4.6836 8.9224 11.33 33.78 4.9867 15.5795
37.50 0.4119 0.2625 4.5949 8.8349 11.16 33.66 4.9935 15.5878
38.50 0.4089 0.2603 4.5487 8.7098 11.12 33.46 4.9828 15.6036
39.50 0.4077 0.2589 4.3694 8.3748 10.72 32.35 4.9626 15.5735
40.50 0.4062 0.2572 4.3097 8.0917 10.61 31.46 4.9543 15.5708
41.50 0.4036 0.2553 4.2586 8.0849 10.55 31.67 4.9556 15.5610
42.50 0.4018 0.2535 4.2029 7.7776 10.46 30.68 4.9604 15.5654
43.50 0.4009 0.2529 4.1368 7.6835 10.32 30.38 4.9456 15.5897
Table 4
Transmutation characteristics of a two-zone subcritical model with heterogeneous fuel composition (System ІІ)
Rint, сm
σf
Np-237
,
barn
σf
Am-243
,
barn
σc
Np-237
,
barn
σc
Am-243
,
barn
α
Np-237
α
Am-243
σc
I-129
,
barn
σc
Tc-99
,
barn
1 2 3 4 5 6 7 8 9
10.50 0.5341 0.3852 10.0698 20.2898 18.85 52.68 6.5009 15.7011
11.50 0.5288 0.3763 9.0191 18.1078 17.06 48.12 6.4658 15.6882
12.50 0.5247 0.3700 8.4916 17.3700 16.18 46.95 6.4441 15.6604
13.50 0.5189 0.3633 8.0888 16.9456 15.59 46.64 6.4124 15.6805
14.50 0.5134 0.3561 7.5780 15.6143 14.76 43.85 6.3895 15.6573
15.50 0.5094 0.3502 7.1034 14.5061 13.95 41.42 6.3622 15.6550
16.50 0.5049 0.3445 6.6933 13.6417 13.26 39.60 6.3347 15.6299
17.50 0.5024 0.3410 6.3384 12.8949 12.62 37.82 6.3095 15.6308
18.50 0.4976 0.3360 6.0730 12.2299 12.20 36.40 6.2808 15.6225
19.50 0.4934 0.3308 5.8314 11.6141 11.82 35.11 6.2497 15.6016
20.50 0.4895 0.3263 5.5606 10.9183 11.36 33.46 6.2278 15.5818
21.50 0.4870 0.3230 5.3144 10.6487 10.91 32.97 6.1952 15.5762
22.50 0.4829 0.3193 5.1392 10.1364 10.64 31.75 6.1676 15.5817
23.50 0.4804 0.3164 4.9452 9.6248 10.29 30.42 6.1385 15.5640
24.50 0.4774 0.3133 4.7966 9.2815 10.05 29.63 6.1184 15.5571
25.50 0.4749 0.3099 4.6047 8.8945 9.70 28.70 6.0831 15.5593
26.50 0.4717 0.3072 4.4137 8.5807 9.36 27.93 6.0485 15.5449
27.50 0.4686 0.3039 4.3355 8.2401 9.25 27.12 6.0238 15.5351
28.50 0.4672 0.3023 4.2592 8.2904 9.12 27.42 5.9917 15.5302
29.50 0.4638 0.2995 4.1091 8.0165 8.86 26.77 5.9576 15.5198
30.50 0.4617 0.2971 3.9327 7.2707 8.52 24.47 5.9271 15.4959
31.50 0.4587 0.2945 3.8905 7.2487 8.48 24.62 5.9032 15.4882
32.50 0.4585 0.2940 3.8242 7.2105 8.34 24.52 5.8773 15.4663
33.50 0.4549 0.2901 3.7054 6.8724 8.15 23.69 5.8303 15.4657
34.50 0.4527 0.2885 3.6180 6.7184 7.99 23.29 5.7983 15.4582
35.50 0.4512 0.2866 3.4957 6.4257 7.75 22.42 5.7573 15.4628
36.50 0.4495 0.2850 3.4347 6.3602 7.64 22.32 5.7348 15.4267
37.50 0.4478 0.2836 3.4046 6.2396 7.60 22.00 5.7106 15.4377
38.50 0.4451 0.2811 3.3658 6.0308 7.56 21.45 5.6692 15.4060
39.50 0.4426 0.2788 3.2409 5.8611 7.32 21.02 5.6294 15.3977
40.50 0.4421 0.2780 3.1696 5.6236 7.17 20.23 5.5841 15.3929
41.50 0.4411 0.2773 3.1047 5.4582 7.04 19.69 5.5476 15.3609
42.50 0.4393 0.2756 3.0641 5.4124 6.97 19.64 5.5217 15.3763
43.50 0.4379 0.2743 3.0098 5.2986 6.87 19.31 5.4693 15.3646
44.50 0.4362 0.2726 2.9317 5.1045 6.72 18.72 5.4240 15.3168
45.50 0.4349 0.2718 2.8825 5.0096 6.63 18.43 5.3911 15.3075
46.50 0.4329 0.2698 2.8513 4.8816 6.59 18.09 5.3456 15.2828
47.50 0.4320 0.2690 2.8021 4.8333 6.49 17.97 5.3140 15.3056
48.50 0.4316 0.2685 2.7554 4.6937 6.38 17.48 5.2667 15.2789
49.50 0.4304 0.2675 2.7065 4.6015 6.29 17.20 5.2037 15.2456
50.50 0.4300 0.2668 2.6749 4.4728 6.22 16.76 5.1687 15.2293
The designations in Tables 3 and 4 include the
following values: Rint – the inner zone radius, cm; σf
Np-237
– the microscopic cross-section of the fission reaction for
Np-237 in the inner zone, barn; σf
Am-243
– the microscopic
cross-section of the fission reaction for Am-243 in the
inner zone, barn; σc
Np-237
– the microscopic cross-section
of the capture reaction for Np-237 in the inner zone, barn;
σc
Am-243
– the microscopic cross-section of the capture
reaction for Am-243 in the inner zone, barn; α
Np-237
– the
microscopic cross-section of the capture reaction ratio to
the microscopic cross-section of the fission reaction for
Np-237 in the inner zone [22]; α
Am-243
– the microscopic
cross-section of the capture reaction ratio to the
microscopic cross-section of the fission reaction for
Am-243 in the inner zone; σc
I-129
– microscopic cross-
section of the capture reaction for I-129 in the outer zone,
barn; σc
Tc-99
– microscopic cross-section of the capture
reaction for Tc-99 in the outer zone, barn. Microscopic
cross-sections are calculated as averaged over the
specified zones entire volume. From Tabl. 3 for System I,
it is clearly seen that with increasing the inner zone
volume, the transmutation characteristics of the system
for minor actinides considerably improve. It can be seen
that parameter α decreases by almost 2.4 times for
Np-237 and for Am-243 parameter α decreases by almost
2.23 times. At the same time the transmutation
characteristics for long-lived fission products are reduced
slightly (up to 6% for I-129). From Tabl. 4 for System II,
the same is seen with increasing the inner zone volume:
the transmutation characteristics of the system for minor
actinides considerably improve; parameter α decreases by
almost 3 times for Np-237 and for Am-243 parameter α
decreases by almost 3.15 times. At the same time the
microscopic cross-sections of the capture reaction for
long-lived fission products decrease slightly for the
thermal zone.
Comparing the System I and Systems II transmutation
characteristics, the following can be noted: a) the division
cross-sections for minor actinides are higher for System
II; b) the capture cross-sections for minor actinides are
lower also for System II; c) as a consequence, the α
parameter for System II is much better than for System I,
which allows us to conclude that fuel with 15%
enrichment creates better conditions for minor actinides
transmutation than fuel with a 10% enrichment; d) System
II has a higher capture cross-section than System I for
iodine and a bit lower for technetium. Summing up the
comparison of the presented systems, it can be concluded
that System II has better transmutation characteristics for
both minor actinides and for long-lived fission products
(iodine-129).
These results give an opportunity to select the
geometric and material characteristics of the research
two-zone subcritical reactor in such a way that neutron
and transmutation parameters meet the purposes of
creating this reactor.
CONCLUSIONS
A two-zone subcritical reactor model with fast
neutron spectra and the thermal one in the internal and
external zones was developed using Serpent code. At the
same time the uranium-235 enrichment maximum level
did not exceed 10…15% which complies with the IAEA
recommendations for new subcritical reactors projects
[6].
An optimization modeling of the two-zone subcritical
system main neutron, economic and transmutation
characteristics for various geometric parameters was
carried out.
It was shown that it is possible to choose the two-zone
subcritical system fuel composition and geometry in such
a way that the system transmutation and neutron
characteristics and the fuel cost fulfill the purposes of
creating a research subcritical reactor.
APPRECIATION
This research was carried out with the financial
support of the IAEA, within the terms and conditions of
the Research Contract 20638 in the framework of the
Coordinated Research Project (CRP) “Accelerator Driven
Systems (ADS) Applications and use of Low-Enriched
Uranium in ADS (T33002)” within the project “The
Two-Zone Subcritical Systems with Fast and Thermal
Neutron Spectra for Transmutation of Minor Actinides
and Long-Lived Fission Products”. The authors is
grateful to Galyna Danyliuk and Alina Dembitskaya for
the help in preparing this article.
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Article received 15.01.2018
ИССЛЕДОВАНИЕ ГЕОМЕТРИИ И ТОПЛИВНОГО СОСТАВА ДВУХЗОННОГО
ПОДКРИТИЧЕСКОГО ЯДЕРНОГО РЕАКТОРА ДЛЯ ТРАНСМУТАЦИИ
ЯДЕРНЫХ ОТХОДОВ
Д.О. Шеляговский, В.И. Гулик, А.В. Носовский
Представлены результаты исследований, направленных на оптимизацию топливного состава
двухзонного подкритического ядерного реактора. В рамках данной работы были выполнены исследования
двухзонного подкритического реактора с гетерогенным составом топлива в отношении геометрических,
материальных и экономических параметров рассмотренной системы. Также был выполнен расчет
трансмутационных характеристик системы для основных изотопов, которые относятся к проблемным
элементам радиоактивных отходов действующих ядерных реакторов. Было показано, что можно подобрать
материальные и геометрические характеристики двухзонной подкритической системы таким образом, чтобы
это удовлетворяло целям создания подкритического реактора в отношении величины потока нейтронов,
трансмутационных параметров и стоимости системы.
ДОСЛІДЖЕННЯ ГЕОМЕТРІЇ І ПАЛИВНОГО СКЛАДУ ДВОЗОННОГО
ПІДКРИТИЧНОГО ЯДЕРНОГО РЕАКТОРА ДЛЯ ТРАНСМУТАЦІЇ ЯДЕРНИХ ВІДХОДІВ
Д.О. Шеляговський, В.І. Гулік, А.В. Носовський
Представлені результати досліджень, спрямованих на оптимізацію паливного складу двозонного
підкритичного ядерного реактора. В рамках даної роботи були виконані дослідження двозонного
підкритичного реактора з гетерогенним складом палива відносно геометричних, матеріальних і економічних
параметрів розглянутої системи. Також було виконано розрахунок трансмутаційних характеристик системи
для основних ізотопів, які відносяться до проблемних елементів радіоактивних відходів діючих ядерних
реакторів. Було показано, що можна підібрати матеріальні і геометричні характеристики двозонної
підкритичній системи таким чином, щоб це задовольняло цілям створення підкритичного реактора щодо
величини потоку нейтронів, трансмутаційних параметрів і вартості системи.
https://www-nds.iaea.org/exfor/endf.htm
|
| id | nasplib_isofts_kiev_ua-123456789-147066 |
| institution | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| issn | 1562-6016 |
| language | English |
| last_indexed | 2025-12-02T09:26:03Z |
| publishDate | 2018 |
| publisher | Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| record_format | dspace |
| spelling | Sheliahovskyi, D.O. Gulik, V.I. Nosovskyi, A.V 2019-02-13T15:11:30Z 2019-02-13T15:11:30Z 2018 Investigation of geometry and fuel composition in two-zone subcritical research reactor for nuclear waste transmutation / D.O. Sheliahovskyi, V.I. Gulik, A.V. Nosovskyi // Вопросы атомной науки и техники. — 2018. — № 2. — С. 50-56. — Бібліогр.: 22 назв. — англ. 1562-6016 https://nasplib.isofts.kiev.ua/handle/123456789/147066 621.384.6 The investigations directed to optimization of fuel compositions for two-zone subcritical reactor is considered in present paper. The study of two-zone subcritical reactor with heterogeneous fuel regard to geometrical, material and economical characteristics was carried out within the scope of this paper. The calculations of transmutation characteristics for main isotopes regard to radioactive waste from conventional nuclear reactors was carried out. There is a possibility for selection of material and geometrical characteristics of two-zone subcritical system in such a way as to satisfy the objectives for development of subcritical reactor in relation to the magnitude of the neutron flux, the transmutation parameters and the cost of system. Представлені результати досліджень, спрямованих на оптимізацію паливного складу двозонного підкритичного ядерного реактора. В рамках даної роботи були виконані дослідження двозонного підкритичного реактора з гетерогенним складом палива відносно геометричних, матеріальних і економічних параметрів розглянутої системи. Також було виконано розрахунок трансмутаційних характеристик системи для основних ізотопів, які відносяться до проблемних елементів радіоактивних відходів діючих ядерних реакторів. Було показано, що можна підібрати матеріальні і геометричні характеристики двозонної підкритичній системи таким чином, щоб це задовольняло цілям створення підкритичного реактора щодо величини потоку нейтронів, трансмутаційних параметрів і вартості системи. Представлены результаты исследований, направленных на оптимизацию топливного состава двухзонного подкритического ядерного реактора. В рамках данной работы были выполнены исследования двухзонного подкритического реактора с гетерогенным составом топлива в отношении геометрических, материальных и экономических параметров рассмотренной системы. Также был выполнен расчет трансмутационных характеристик системы для основных изотопов, которые относятся к проблемным элементам радиоактивных отходов действующих ядерных реакторов. Было показано, что можно подобрать материальные и геометрические характеристики двухзонной подкритической системы таким образом, чтобы это удовлетворяло целям создания подкритического реактора в отношении величины потока нейтронов, трансмутационных параметров и стоимости системы. en Національний науковий центр «Харківський фізико-технічний інститут» НАН України Вопросы атомной науки и техники Проблемы современной ядерной энергетики Investigation of geometry and fuel composition in two-zone subcritical research reactor for nuclear waste transmutation Дослідження геометрії і паливного складу двозонного підкритичного ядерного реактора для трансмутації ядерних відходів Исследование геометрии и топливного состава двухзонного подкритического ядерного реактора для трансмутации ядерных отходов Article published earlier |
| spellingShingle | Investigation of geometry and fuel composition in two-zone subcritical research reactor for nuclear waste transmutation Sheliahovskyi, D.O. Gulik, V.I. Nosovskyi, A.V Проблемы современной ядерной энергетики |
| title | Investigation of geometry and fuel composition in two-zone subcritical research reactor for nuclear waste transmutation |
| title_alt | Дослідження геометрії і паливного складу двозонного підкритичного ядерного реактора для трансмутації ядерних відходів Исследование геометрии и топливного состава двухзонного подкритического ядерного реактора для трансмутации ядерных отходов |
| title_full | Investigation of geometry and fuel composition in two-zone subcritical research reactor for nuclear waste transmutation |
| title_fullStr | Investigation of geometry and fuel composition in two-zone subcritical research reactor for nuclear waste transmutation |
| title_full_unstemmed | Investigation of geometry and fuel composition in two-zone subcritical research reactor for nuclear waste transmutation |
| title_short | Investigation of geometry and fuel composition in two-zone subcritical research reactor for nuclear waste transmutation |
| title_sort | investigation of geometry and fuel composition in two-zone subcritical research reactor for nuclear waste transmutation |
| topic | Проблемы современной ядерной энергетики |
| topic_facet | Проблемы современной ядерной энергетики |
| url | https://nasplib.isofts.kiev.ua/handle/123456789/147066 |
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