Experimental studies of the nuclear-physical characteristics of the extended uranium target irradiated by relativistic protons, deutrons and ¹²C nuclei
In 2011-2017 in the framework of the international collaboration project “Energy and Transmutation of RAW”, a series of experimental studies on the deep subcritical uranium assembly QUINTA were carried out. The massive uranium target (512 kg of ⁿᵃᵗU) was irradiated with 0.66 GeV proton, deuterons an...
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| Zitieren: | Experimental studies of the nuclear-physical characteristics of the extended uranium target irradiated by relativistic protons, deutrons and ¹²C nuclei / A.A. Zhadan, V.V. Sotnikov, V.A. Voronko, A.A. Baldin, S.I. Tyutyunnikov, O.V. Bukhal, K.V. Husak, I.V. Zhuk, P. Zhivkov // Problems of atomic science and tecnology. — 2020. — № 3. — С. 136-142. — Бібліогр.: 29 назв. — англ. |
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irk-123456789-1945532023-11-27T15:47:18Z Experimental studies of the nuclear-physical characteristics of the extended uranium target irradiated by relativistic protons, deutrons and ¹²C nuclei Zhadan, A.A. Sotnikov, V.V. Voronko, V.A. Baldin, A.A. Tyutyunnikov, S.I. Bukhal, O.V. Husak, K.V. Zhuk, I.V. Zhivkov, P. Experimental methods and processing of data In 2011-2017 in the framework of the international collaboration project “Energy and Transmutation of RAW”, a series of experimental studies on the deep subcritical uranium assembly QUINTA were carried out. The massive uranium target (512 kg of ⁿᵃᵗU) was irradiated with 0.66 GeV proton, deuterons and ¹²C nuclei (1 to 4 AGeV) from the Phasotron and Nuclotron accelerators (JINR, Dubna). The main results of experimental studies carried out with the participation of the Kharkov group of collaboration are presented. У 2011-2017 рр. у рамках Міжнародної колаборації «Енергія і трансмутація РАВ» було проведено серію експериментальних досліджень на глибоко підкритичній урановій збірці «КВІНТА». Масивна уранова мішень (512 кг ⁿᵃᵗU) збірки опромінювалася 0,66 ГеВ протонами, дейтронами і ядрами ¹²С (1…4 ГеВ/нукл.) від прискорювачів Фазотрон і Нуклотрон (ОІЯД, м. Дубна). Наведено основні результати експериментальних досліджень, які було виконано за участю харківської групи колаборації. В 2011-2017 гг. в рамках Международной коллаборации «Энергия и трансмутация РАО» была проведена серия экспериментальных исследований на глубоко подкритической урановой сборке «КВИНТА». Массивная урановая мишень (512 кг ⁿᵃᵗU) сборки облучалась 0,66 ГэВ протонами, дейтронами и ядрами ¹²С (1…4 ГэВ/нукл.) от ускорителей Фазотрон и Нуклотрон (ОИЯИ, г. Дубна). Представлены основные результаты экспериментальных исследований, выполненных при участии харьковской группы коллаборации. 2020 Article Experimental studies of the nuclear-physical characteristics of the extended uranium target irradiated by relativistic protons, deutrons and ¹²C nuclei / A.A. Zhadan, V.V. Sotnikov, V.A. Voronko, A.A. Baldin, S.I. Tyutyunnikov, O.V. Bukhal, K.V. Husak, I.V. Zhuk, P. Zhivkov // Problems of atomic science and tecnology. — 2020. — № 3. — С. 136-142. — Бібліогр.: 29 назв. — англ. 1562-6016 PACS: 28.41. Kw, 28.50. Ft http://dspace.nbuv.gov.ua/handle/123456789/194553 en Вопросы атомной науки и техники Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
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Experimental methods and processing of data Experimental methods and processing of data |
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Experimental methods and processing of data Experimental methods and processing of data Zhadan, A.A. Sotnikov, V.V. Voronko, V.A. Baldin, A.A. Tyutyunnikov, S.I. Bukhal, O.V. Husak, K.V. Zhuk, I.V. Zhivkov, P. Experimental studies of the nuclear-physical characteristics of the extended uranium target irradiated by relativistic protons, deutrons and ¹²C nuclei Вопросы атомной науки и техники |
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In 2011-2017 in the framework of the international collaboration project “Energy and Transmutation of RAW”, a series of experimental studies on the deep subcritical uranium assembly QUINTA were carried out. The massive uranium target (512 kg of ⁿᵃᵗU) was irradiated with 0.66 GeV proton, deuterons and ¹²C nuclei (1 to 4 AGeV) from the Phasotron and Nuclotron accelerators (JINR, Dubna). The main results of experimental studies carried out with the participation of the Kharkov group of collaboration are presented. |
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Article |
| author |
Zhadan, A.A. Sotnikov, V.V. Voronko, V.A. Baldin, A.A. Tyutyunnikov, S.I. Bukhal, O.V. Husak, K.V. Zhuk, I.V. Zhivkov, P. |
| author_facet |
Zhadan, A.A. Sotnikov, V.V. Voronko, V.A. Baldin, A.A. Tyutyunnikov, S.I. Bukhal, O.V. Husak, K.V. Zhuk, I.V. Zhivkov, P. |
| author_sort |
Zhadan, A.A. |
| title |
Experimental studies of the nuclear-physical characteristics of the extended uranium target irradiated by relativistic protons, deutrons and ¹²C nuclei |
| title_short |
Experimental studies of the nuclear-physical characteristics of the extended uranium target irradiated by relativistic protons, deutrons and ¹²C nuclei |
| title_full |
Experimental studies of the nuclear-physical characteristics of the extended uranium target irradiated by relativistic protons, deutrons and ¹²C nuclei |
| title_fullStr |
Experimental studies of the nuclear-physical characteristics of the extended uranium target irradiated by relativistic protons, deutrons and ¹²C nuclei |
| title_full_unstemmed |
Experimental studies of the nuclear-physical characteristics of the extended uranium target irradiated by relativistic protons, deutrons and ¹²C nuclei |
| title_sort |
experimental studies of the nuclear-physical characteristics of the extended uranium target irradiated by relativistic protons, deutrons and ¹²c nuclei |
| publisher |
Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| publishDate |
2020 |
| topic_facet |
Experimental methods and processing of data |
| url |
http://dspace.nbuv.gov.ua/handle/123456789/194553 |
| citation_txt |
Experimental studies of the nuclear-physical characteristics of the extended uranium target irradiated by relativistic protons, deutrons and ¹²C nuclei / A.A. Zhadan, V.V. Sotnikov, V.A. Voronko, A.A. Baldin, S.I. Tyutyunnikov, O.V. Bukhal, K.V. Husak, I.V. Zhuk, P. Zhivkov // Problems of atomic science and tecnology. — 2020. — № 3. — С. 136-142. — Бібліогр.: 29 назв. — англ. |
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Вопросы атомной науки и техники |
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ISSN 1562-6016. ВАНТ. 2020. №3(127) 136
EXPERIMENTAL STUDIES OF THE NUCLEAR-PHYSICAL
CHARACTERISTICS OF THE EXTENDED URANIUM TARGET
IRRADIATED BY RELATIVISTIC PROTONS, DEUTRONS
AND 12C NUCLEI
A.A. Zhadan1, V.V. Sotnikov1, V.A. Voronko1, A.A. Baldin2, S.I. Tyutyunnikov2, O.V. Bukhal3,
K.V. Husak3, I.V. Zhuk3, P. Zhivkov4
1National Science Center “Kharkov Institute of Physics and Technology”, Kharkiv, Ukraine;
2Joint Institute for Nuclear Research, Dubna, Russia;
3Joint Institute for Power and Nuclear Research – SOSNY, Minsk, Belarus;
4Institute for Nuclear Research and Nuclear Energy, Sofia, Bulgaria
E-mail: zhadan@kipt.kharkov.ua
In 2011-2017 in the framework of the international collaboration project “Energy and Transmutation of RAW”,
a series of experimental studies on the deep subcritical uranium assembly QUINTA were carried out. The massive
uranium target (512 kg of natU) was irradiated with 0.66 GeV proton, deuterons and 12C nuclei (1 to 4 AGeV) from
the Phasotron and Nuclotron accelerators (JINR, Dubna). The main results of experimental studies carried out with
the participation of the Kharkov group of collaboration are presented.
PACS: 28.41. Kw, 28.50. Ft
INTRODUCTION
The increased in the past two decades interest in the
study of subcritical accelerator-driven systems (ADS)
for the purpose of using them to solve applied problems
led to theoretical and experimental studies in this field
in the world's leading nuclear centers. At the present
time the powerful multipurpose accelerator centers such
as SNS, USA (~1.3 MW power) [1], J-PARC, Japan
(~1 MW) [2], the PSI, Switzerland (~0.75 MW) [3]
have been operated. They have different departments in
structure that study materials, transmutation of radioac-
tive waste, medical radioisotopes production, etc. These
centers use proton accelerators with energies of about
1 GeV (or less) for neutron generation. Mean while, a
number of experiments have studied neutron production
in thick targets (JINR, LANL, KEK, and ITEP), and
found that more energy accelerator should be used for
more effective neutron generation. In particular, the
group of V. Yurevich (JINR, Dubna) performed the
cycle of experimental studies [4, 5] and analysis of
available experimental data of neutron energy spectra
that produced in thick targets. It was shown that for
thick targets secondary nuclear interactions in the target
give additional contribution to neutron emission. Neu-
tron multiplication with simultaneous weakening of the
charged particle release makes thick target, especially as
neutron sources. The ratio of total energy expended on
the neutron formation to particle beam energy shows
weak growth with beam energy and does not depend on
type of particle primary beam. The effect of average neu-
tron energy increasing per unit of beam energy with in-
creasing of beam energy has also been noted. That could
be used for further neutron multiplication when using a
quasi-infinite target. In this context, a more efficient use
of beam energy for neutron production will significantly
increase the value of optimum beam particle energy.
Within the framework of the international project
"Energy and Transmutation of RAW" a series of ex-
periments aimed at the new ADS concept (relativistic
nuclear technology – RNT [6]) verification was carried
out in 2011-2017 at the Nuclotron and Phasotron accel-
erators (JINR, Dubna).
The basic physical idea of this approach is to use
natural (depleted) uranium or thorium to create an ADS
with a deep subcritical quasi-infinite (with negligible
neutron leakage) multiplying target irradiated with pro-
tons, deuterons, or light nuclei with energy in the range
1…5 AGeV and possibly higher. Such scheme can pro-
vide extremely hard neutron spectrum within the sub-
critical active core and ensure an effective burning of
core material as well as spent nuclear fuel added to the
initial core.
The experiments ("Energy and Transmutation of
RAW") were carried out with a target assembly (TA)
Quinta [6] which containing 512 kg of natural uranium
surrounded by a lead shield. Schematic drawing of
Quinta setup is presented on Fig. 1. The TA Quinta was
irradiated with 0.66 GeV protons, and deuterons and
carbon ions with energy in the range 1…4 AGeV.
In this work the main results of experimental studies
carried out with the participation of the Kharkov group
of collaboration are presented.
In our experiments [7 - 15], spatial distributions of
the 239Pu production rates and 238U fission were studied,
and the 238U fission total number and 239Pu production
in the volume of the uranium target was estimated; ex-
perimental dependences of the total number of uranium
fission and accumulated 239Pu on the energy and type of
the primary beam particles were obtained; the spatial
distributions of 59Co(n, x) reaction rates in a wide range
of threshold energies from 0 to 70 MeV were investi-
gated; the beam power gains were obtained and these
values were extrapolated for a quasi-infinite uranium
target; the reaction rates of the minor actinides transmu-
tation in the neutron spectra of the uranium target have
been studied. The obtained experimental results were
compared with model calculations.
1. EXPERIMENT AND METHODS
The uranium target of the TA Quinta (see Fig. 1)
consists of 5 hexagonal sections (114 mm in length,
ISSN 1562-6016. ВАНТ. 2020. №3(127) 137
350 mm in height) filled with metallic natural uranium
cylindrical rods. The total mass of uranium in 5 sections
of the target is ≈ 512 kg. The uranium fill factor is about
0.6. Quinta is a deep subcritical assembly with
keff ≈ 0.22. The uranium target is placed inside 10 cm
thick lead blanket.
Fig. 1. Uranium target QUINTA with detector plates.
The natural uranium mass for each section 104.92 kg
Before, between and behind of the uranium target
sections in 17 mm gaps, detector plates are mounted. On
these plates the various types of activation and track
detectors are placed. For more detailed description of
TA Quinta and detectors location, see [8, 13].
The uranium target was irradiated with 0.66 GeV
protons, 1, 2, 4, and 8 GeV deuteron and with 24 and
48 GeV carbon beams from the Nuclotron and Phas-
otron accelerators of the JINR. The total number of pro-
tons, deuterons and 12C ions to hit the target was deter-
mined from the activation of Al and Cu foils in the
27Al(a, x)24Na and natCu(a, x)24Na reaction. Detailed
information of the beam monitoring is published in [18,
19]. The beam shape and beam positioning on the target
were determined using the track detector technique [17].
To determine the spatial neutron flux distribution
and the reactions caused by them in the volume of the
uranium target various types of the activation and track
detectors have been used.
After the end of irradiation, the activation detectors
taken out from the target to measure γ-spectra using
HPGe detectors. Detection efficiency curves of detec-
tors for various measurement positions were constructed
using the following standard gamma sources: 54Mn,
57Co, 60Co, 88Y, 109Cd, 113Sn, 133Ba, 137Cs, 139Ce, 152Eu,
228Th, and 241Am.
For 238U(n, γ) and natU(n, f) reaction rate measure-
ments the activation detectors from natural metallic ura-
nium (diameter 8 mm, thickness 1 mm, mass ~ 0.9 g)
were used. In each irradiation 29 activation detectors
were used. These detectors were mounted onto six re-
movable detector plates (see Fig. 1) at 0, 4, 8, and 12 cm
(R) from target axis (Z).
The number of neutron radiation capture reactions
was determined by the yield of γ-line with 277.6 keV
accompanying 239Np decay:
238U(n,γ)239U (β– 23.5 m) → 239Np (β– 2,4 d) →239Pu.
Fissions reaction rates were determined by yield of
gamma-lines 743.4, 364.5, 529.9 (87%), and 293.3 keV
which accompany decay of fission products 97Zr, 131I,
133I, and 143Ce respectively. Cumulative yields (CY) of
these masses of products not greatly changed in a wide
range of neutron energies (see more detail ref. [13]). We
used the following values of CY: 97Zr 5.4%, 131I
3.6%, 133I 6.4%, 143Ce 4.3% (average evaluated data
for fission spectrum and 14 MeV neutrons). Fission
rates obtained for 97Zr, 131I, 133I, and 143Ce are averaged.
The overall uncertainties of the reaction rates ob-
tained through gamma spectroscopy method are
12…15%, mainly due to errors in cross-section of moni-
tor reactions.
2. MONTE CARLO SIMULATIONS
The irradiation of the Quinta assembly was simu-
lated using MCNPX 2.7 code [20]. The INCL4-ABLA
physics model and LAQGSM code were used. The neu-
tron and charge particle spectrum at the location of irra-
diated samples was calculated and then the convolution
with cross-sections from ENDF/B-VII evaluation [21]
and from TENDL-2014 [22]. In the simulation the de-
tailed geometric model of the target QUINTA and ex-
perimental data about beam shape and position on the
target were employed.
3. RESULTS AND DISCUSSION
3.1. SPATIAL DISTRIBUTION AND TOTAL
NUMBER OF FUSSION AND CAPTURE
REACTIONS
Fig. 2 shows the experimental axial distribution of
natU fission rates for deuteron and 12C ion primary
beams with various energies. Value of reaction rates
normalized per one gram of natU, per one incident parti-
cle and per 1 GeV particle energy.
0.00
0.50
1.00
1.50
2.00
2.50
3.00
3.50
4.00
0 100 200 300 400 500 600 700
Z, mm
N(fission)/g/particle/GeV, *10-5
D 1 GeV
D 2 Gev
D 4 GeV
D 8 GeV
0.00
0.50
1.00
1.50
2.00
2.50
3.00
0 200 400 600
Z, mm
C12 24 GeV
C12 48 GeV
Fig. 2. Axial distributions of natU(n, f) reaction rates
average over radial distribution at each detector plate
For this normalization, the distributions of reaction
rates of one type of primary particles are close together
for all beam energies. But one can see that with increas-
ing beam energy, a relative decrease in the number of
reactions at the first half of the target is observed in the
axial distributions of uranium fission events, and a
slight increase in these quantities is observed at the
same time at the second half of the target along the di-
rection of the primary beam.
Axial distributions of capture reaction rates are simi-
lar to axial distributions of fission reaction rates.
Based on spatial distributions of neutron capture and
fissions reactions (both for experimental values and
simulated using MCNPX 2.7) the total number of 239Pu
production and the total number of natU fissions were
obtained in the volume of uranium target (Figs. 3 and
ISSN 1562-6016. ВАНТ. 2020. №3(127) 138
4). Estimation of these values was carried out in the
approximation of the cylindrical target with a radius
R = 140 mm (inscribed circle radius of uranium sec-
tions). The radial distance between the activation detec-
tors and the primary beam axis calculated taking into
account beam position at the front end of the target.
4
5
6
7
8
9
10
11
12
0 1 2 3 4
E, AGeV
N(fission)/particle/GeV
D, experiment
MCNPX interp.
4
5
6
7
8
9
10
11
12
1 2 3 4
E, AGeV
12C, experiment
12C, MCNPX
Fig. 3. Integral numbers of natU(n, f) reactions in the
volume of uranium target as a function of beam energy
4
6
8
10
12
14
16
0 1 2 3 4
E, AGeV
N(capture)/particle/GeV
D, experiment
MCNPX interp.
4
6
8
10
12
14
16
1 2 3 4
E, AGeV
12C, experiment
12C, MCNPX
Fig. 4. Integral numbers of 238U(n, γ) reactions in the
volume of uranium target as a function of beam energy
The integral number of fissions reactions (Nf) in the
volume of uranium target of QUINTA, that was ob-
tained by means of gamma spectroscopy, remains ap-
proximately constant within our 14% of the experimen-
tal errors for 1, 2, 4, and 8 GeV deuteron (per a deuteron
and per 1 GeV energy of the beam or per unit of pri-
mary beam power). The integral number of fission reac-
tions for carbon beams is smaller than for deuteron
beams by 20…25%.
For the integral number of capture reactions (Nc) we
have seen maximum at 2 GeV (1 GeV per nucleon) for
deuteron beam. With a further increase in the beam en-
ergy, the Nc values decrease.
MCNPX code simulation of integral number of fis-
sions and capture reactions is in agreement with the
experimental data in the range of 20%. In case of carbon
beam, we have 35% deviation between experimental
and simulated data.
Another discrepancy between the experiment and
the Monte Carlo calculation is shown in Fig. 5. Fig. 5
shows the axial distribution of natU fission rates for six
uranium samples at R = 8 cm. As can be seen in the case
of the 2 GeV deuteron beam there is a good agreement
between the calculation and experiment. But with in-
creasing beam energy there is an increasing discrepancy
between the experimental and calculated data only for
the first three detector plates (Z = 0, 123, and 254 mm).
Such a discrepancy in backward direction from beam
path in target is also observed for samples at R = 4 cm
and 12 cm.
0.10
1.00
10.00
0 100 200 300 400 500 600 700
Z, mm
N(fission)/g/particle/GeV, *10-5
D, 2 Gev Exp R =8 cm
D, 2 GeV MCNPX R =8 cm
0.10
1.00
10.00
0 100 200 300 400 500 600 700
Z, mm
D 4 Gev Exp
D, 4 GeV MCNPX R
0.10
1.00
10.00
0 100 200 300 400 500 600 700
Z, mm
D 8 Gev Exp
D 8 GeV MCNPX
0.10
1.00
10.00
0 100 200 300 400 500 600 700
Z, mm
12C 48 GeV, Exp.
12C 48 GeV, MCNPX
Fig. 5. Axial distributions of natU fission rates
for samples at radial distances of R = 8 cm.
Experimental and Monte Carlo calculation
3.2. 59Co(n, x) REACTION RATES
The spatial distribution of particle fluences in the ex-
tended uranium target ("Quinta" assembly) irradiated by
0.66 GeV proton, 1, 2, 4 AGeV deuteron and 2, 4 AGeV
carbon beams is studied by analyzing the accumulation
rates of the isotopes with different threshold energy (Eth)
in 59Co samples. The accumulation rates for the follow-
ing isotopes: 60Co (Eth ≈ 0 MeV), 59Fe (Eth ≈ 3 MeV),
58Co (Eth ≈ 10 MeV), 57Co (Eth ≈ 20 MeV), 56Co (Eth ≈
32 MeV), 47Sc (Eth ≈ 55 MeV), and 48V (Eth ≈ 70 MeV)
were measured [7, 10] using the HPGe spectrometers. It
was found that neutron spectrum hardening in the ura-
nium target of assembly "QUINTA" was observed with
increasing of deuteron energy.
Fig. 6 shows dependence of reaction rates ratio
R= 59Co(n, x)48V/59Co(n, p)59Fe (1)
from deuteron energy (normalized to 2 GeV). This ratio
does not include the errors from the beam intensity
measurements. The maximum cross section of 59Fe pro-
duction take place at neutron energy En ~ 13 MeV
(threshold energy Eth ≈ 3 MeV), while the maximum
cross section of 48V production take place at
En ~ 160 MeV (Eth ≈ 70 MeV) [22]. This reaction rates
ratio increases with increasing of energy of primary
deuteron beam.
As an example, Fig. 7 shows the axial distributions of
reaction rate 59Co(n, p)59Fe and 59Co(n, x)48V for deuter-
ons with energy Ed = 2 and 4 AGeV. The figure analysis
shows, that the number of neutrons with energies above
100 MeV increases with increasing of deuteron energy
from 2 to 4 AGeV, but at the same time the number of
neutrons with energies less than 30 MeV decreases.
The experimental results were compared with the
simulation performed [10] using the code Geant4. The
simulations underestimate the production of isotopes
with high threshold energy. The simulated values of the
accumulation rates after 40 cm of uranium are
1.5…2 times lower than the experimental data.
ISSN 1562-6016. ВАНТ. 2020. №3(127) 139
48V / 59Fe
0.90
0.95
1.00
1.05
1.10
1.15
1.20
1.25
1.30
1.35
0 2 4 6 8 10
Deuteron Energy
Fig. 6. Dependence of the reaction rates ratio
59Co(n,x)48V/59Co(n,p)59Fe from deuteron energy (GeV)
0.0E+00
2.0E-07
4.0E-07
6.0E-07
8.0E-07
1.0E-06
1.2E-06
1.4E-06
1.6E-06
1.8E-06
0 200 400 600 800
N(
59
Fe
)/g
/d
/E
Z, mm
N(59Fe)/D/E 2 AGeV
N(59Fe)/D/E 4 AGeV
0.0E+00
2.0E-08
4.0E-08
6.0E-08
8.0E-08
1.0E-07
1.2E-07
1.4E-07
1.6E-07
0 200 400 600 800
N(
48
V)
/g
/d
/E
Z, mm
N(48V)/d/E 2 AGeV
N(48V)/d/E 4 AGeV
Fig. 7. Axial distribution of reaction rates
59Co(n,p)59Fe (up) and 59Co(n,x)48V (down)
for deuteron energies 2 and 4 AGeV
The experimental data obtained with carbon beam
show that the particle spectra become harder under irra-
diation by carbon in comparison with deuteron beam
with the same energy per nucleon. For example, value R
(1) for the 2 AGeV carbon beam is 1.5-2 times greater
than for the 2 AGeV deuteron beam. The simulation
does not reproduce correctly this effect.
The obtained results demonstrate that it is important
to improve the simulation codes and to continue the
experimental investigations with the extended target
irradiated by light ion beams in an energy range greater
than 2 GeV per nucleon.
3.3. NEUTRON-INDUCED TRANSMUTATION
REACTIONS
Transmutation reactions in the 237Np, 238Pu, and 239Pu
samples were investigated in the neutron field generated
inside uranium target of assembly QUINTA under irra-
diation with 2, 4, and 8 GeV deuteron beams [12].
The neutron-induced transmutation (fission) of the
actinide samples was measured by methods of gamma-
ray spectrometry with HPGe detectors. The experimen-
tal reaction rates of the respective residual nuclei have
been divided by the cumulative fission yields taken from
ENDF/B-VII.1 database. The most reliable results have
been reached when selecting the data for neutron energy
En = 500 keV. The other available energies had provided
results with higher average deviation from the mean.
The following residual nuclei were identified in
transmutation samples:
237Np samples: 92Sr, 97Nb, 97Zr, 132,133,135I, 138Cs, 142La;
238Pu samples: 88Kr, 91,92Sr, 97Nb, 97Zr, 105Rh, 105Ru,
129Sb, 131,132,133,135I, 142La, 143Ce;
238Pu samples: 87,88Kr, 88Rb, 91,92Sr, 91mY, 97Nb, 97Zr,
103,105Ru, 105Rh, 127,128Sn, 129,130Sb, 138Cs, 131m,133m,134Te,
139,140Ba,141,142La, 143Ce.
The average reaction rates for fission per unit beam
energy, per one deuteron and per one atom are shown in
Table 1.
Table 1
Average fission transmutation rates per unit beam energy
Energy 2 GeV 4 GeV 8 GeV
Sample
Transmutation rate
(10-26 atom-1×deuteron-1×GeV-1)
237Np 0.9 ± 0.1 0.8 ± 0.1 0.7 ± 0.1
238Pu 2.4 ± 0.3 3.2 ± 0.3 1.8 ± 0.3
239Pu 4.3 ± 0.5 3.7 ± 0.4 4.0 ± 0.4
The fission transmutation rate per unit beam energy
remains stable within one standard deviation. The
weighted mean over all the provided beam energies is
equal to (0.81 ± 0.08)∙10-26, (2.4 ± 0.4)∙10-26, and
(4.0 ± 0.4)∙10-26 (atom×deuteron×GeV-1) in the case of
237Np, 238Pu, and 239Pu samples, respectively.
Both the 237Np and 239Pu isotopes are generated by
the neutron induced reactions in 238U target of QUINTA
assembly:
238U(n,2n)237U(β–6,75 d)→237Np;
238U(n,γ)239U (β– 23.5 m) 239Np (β– 2,4 d) →239Pu.
At the QUINTA target assembly, the production rate
in 238U target and transmutation rate of the investigated
actinides can be studied simultaneously.
The data in Table 2 show a ratio of 239Pu transmuta-
tion via fission to 239Pu production through the
238U(n,γ)239U reaction.
Table 2
Ratio of the 239Pu transmutation to its production in 238U
Beam energy 2 GeV 4 GeV 8 GeV
Production of 239Pu in 238U (10-26 atom-1×deuteron-1)
1.5 ± 0.2 2.0 ± 0.2 4.2 ± 0.4
Ratio of the transmutation of 239Pu via fission to the
its production through the radiative capture in 238U
5.9 ± 0.2 7.5 ± 0.2 7.7 ± 0.6
In the case of the 2 GeV deuteron beam, the 239Pu
transmutation rate is six times its production in 238U.
The ratio increases with deuteron energy. The ratio is
7.5 for the 4 GeV deuteron beam and 7.7 for the 8 GeV
beam. This serves as the evidence of the transmutation
potential of the uranium spallation target.
ISSN 1562-6016. ВАНТ. 2020. №3(127) 140
For the purpose of validation of radiation transport
programs, the experimental results were compared [12]
with simulations by the MCNPX 2.7 [20] and MARS15
[25] code, see Table 3. The neutron spectra were simu-
lated by the Monte Carlo method at the location of acti-
nide samples for QUINTA target geometry. ENDF/B-
VII database, intranuclear physical model INCL4, evap-
oration model ABLA and LAQGSM03.03 code were
used.
Table 3
Comparison of the fission transmutation rate
between experiment and calculation
Energy 2 GeV 4 GeV 8 GeV
Sample Experiment/Calculation ratio MCNPX
237Np 0.9 ± 0.1 0.9 ± 0.1 0.9 ± 0.1
238Pu 0.8 ± 0.1 1.1 ± 0.1 0.8 ± 0.1
239Pu 0.9 ± 0.1 1.0 ± 0.1 1.1 ± 0.1
Sample Experiment/Calculation ratio MARS15
237Np 0.8 ± 0.1 0.9 ± 0.1 0.7 ± 0.1
238Pu 0.9 ± 0.1 1.4 ± 0.1 0.7 ± 0.1
239Pu 1.2 ± 0.1 1.3 ± 0.1 1.2 ± 0.1
In general, a good agreement between the experi-
mental and calculated reaction rates was found in the
whole interval of provided beam energies for MCNPX
2.7 code employing the INCL4-ABLA event generator.
3.4. ESTIMATION OF THE BEAM POWER GAIN
The beam power gain (or energy gain) G in the mul-
tiplying target is one of the all-important ADS charac-
teristics, indicating its ability to produce energy.
The minimum beam power gain value Gmin required
for the energy reproduction (grid power required to run
the accelerator) for ADS with beam power > 3 MW must
be at least about 9. For more powerful beams
(Pbeam >10…20 MW), it is possible to ensure energy re-
production even at Gmin≈ 6…7.5 (our estimations [14]).
The beam power gain G can be determined by the
following expression:
pffp EEnEG /)( , (2)
where Ep is the accelerated particle energy (GeV), nf is
the number of uranium fissions in the uranium assembly
per one accelerated particle, Ef is the fission energy
(0.197 GeV).
The beam power gain determined in this way ap-
proximately corresponds to the total heat release in the
target assembly normalized per primary ion beam power.
In this case, we assume that only a small fraction of the
primary ion energy out of the extended uranium target
with -quanta and mesons. On the other hand, we
take into account only the basic heat release due to the
uranium fission, without taking into account other pos-
sible exothermic reactions on the secondary particles.
In the series of experiments, the uranium fission rate
spatial distributions inside the Quinta target were ob-
tained for various primary beams: 0.66 GeV protons, 1,
2, 4, and 8 GeV deuterons, and 24 and 48 GeV carbon
ions. The total numbers of fission obtained for the target
assembly (TA) Quinta are shown in Table 4 per one
accelerated particle and per beam power.
Table 4
Total numbers of fission
Beam, GeV Nf /ion Nf/ion/GeV
p(0.66) 4.1 ± 0.3 6.2 ± 0.5
D(1) 8.9 ± 0.6 8.9 ± 0.6
D(2) 19 ± 1 9.7 ± 0.6
D(4) 37 ± 2 9.2 ± 0.5
D(8) 71 ± 4 8.9 ± 0.5
12C(24) 160±20 6.7±0.9
12C(48) 340±40 7.1±0.8
For all primary beams the beam power gain values G
for TA Quinta were determined using the expression
(1). The results are shown in Table 5. The beam power
gain values are in range from 2 to 3 for all beams. The
small values of G are explained by the insufficient di-
mensions of the uranium target used in the experiments,
which leads to a large neutron leakage.
In paper [24] (R.G. Vasilkov et al.) for a large natu-
ral uranium target with a mass of about 3.5 t (due to
asymmetric beam input, the effective mass was about
7 t), the fission total number of 18.5 ± 1.7 per 1 proton
with an energy of 0.66 GeV was obtained. The corre-
sponding beam power gain value is 6.5. This is without
considering the fissions (3-4 fissions) and a small neu-
tron leakage of 10…12%. If taking into account
3 fissions in the central part of the target and neutron
leakage of 11% we can obtain G ~ 8.
Using these results from the paper [24], the beam
power gain values for the TA Quinta were extrapolated
[14] for a quasi-infinite uranium assembly in which all
the generated neutrons are completely utilized (see the
values G∞ in the Table 5).
The estimated G∞ values satisfy the minimum re-
quirements (Gmin > 7) for energy reproduction. At the
same time, simulations for quasi-infinite targets give
significantly lower beam power gain values. For exam-
ple, simulation with the MARS15 code (120 cm diame-
ter uranium target with 110 cm length) gives the maxi-
mum beam power gain value ~ 5.5 for protons with an
energy of 2…4 GeV [26].
Table 5
Beam power gains for assembly Quinta and corre-
sponding estimations for quasi-infinite uranium target
Beam (Energy, GeV) G Quinta G∞
p (0.66) 2.2 -
D (1) 2.7 11
D (2) 2.9 11.6
D (4) 2.9 11.4
D (8) 2.8 11
12C (24) 2.3 8.5
12C (48) 2.4 9
p (0.66) [1] - 8
Simulation with the MCNPX 2.7e code for the qua-
si-infinite depleted uranium target with a mass of
~ 21 t (BURAN setup built in JINR, Dubna [28],
Fig. 8), irradiated by protons and deuterons of 1, 6,
12 GeV, gives beam power gain about 4 [27].
ISSN 1562-6016. ВАНТ. 2020. №3(127) 141
Fig. 8. Buran setup is a cylinder made from depleted
uranium with a replaceable central zone. Uranium
longitude of 1 m and 1.2 m in diameter. The cylinder
is surrounded by 10 cm steel covering. The total mass
of uranium in the target assembly is about 21 t
Simulation with the FLUKA code [29] for BURAN
setup, irradiated by protons and deuterons with the en-
ergy 1 GeV, gives beam power gain about 3.7 and 4.1,
respectively [28].
In terms of further research, first of all, it is neces-
sary to verify experimental results [24] in the experi-
ments with a large spallation target with the minimal
neutron leakage.
CONCLUSIONS
It is shown that, within 14% of the experimental er-
rors, the total number of fissions in the target normal-
ized per unit of primary beam power is practically inde-
pendent of the beam energy, and the total produced plu-
tonium nuclei number in the target decreases with beam
energy for both deuteron and carbon beams. As a con-
sequence, the average spectral index also decreases,
showing a hardening of the neutron spectrum inside the
target with energy of the incident particles increasing.
The integral number of fission and capture reactions
for carbon beams is smaller than for deuteron beams by
20…25% at the same beam power and for beam energy
2…4 GeV/nucleon.
We have seen the large discrepancy between the ex-
perimental and calculated values of reaction rates in
backward direction from beam path in target (first and
second target section) for deuteron and carbon beams
with 2 and 4 GeV/nucleon.
Using activation cobalt detectors, it was found that
neutron spectrum hardening in the uranium target of
assembly "QUINTA" was observed with increasing of
deuteron energy. For this type of particles and their en-
ergy range such experiments were performed for the
first time. The experimental data obtained with carbon
beam show that the particle spectra become harder un-
der irradiation by carbon in comparison with deuteron
beam with the same energy per nucleon. The simulation
does not reproduce correctly this effect.
In the case of the 2 GeV deuteron beam, the 239Pu
transmutation rate is six times its production in 238U.
The ratio increases with deuteron energy. The ratio is
7.5 for the 4 GeV deuteron beam and 7.7 for the 8 GeV
beam. This serves as the evidence of the transmutation
potential of the uranium spallation target.
The estimated beam power gain values for quasi-
infinite spallation target satisfy the minimum require-
ments (Gmin > 7) for energy reproduction. At the same
time, simulations for quasi-infinite targets give signifi-
cantly lower beam power gain values.
Some of obtained results demonstrate that it is im-
portant to improve the simulation codes and to continue
the experimental investigations with the extended ADS
target. According to the Monte Carlo simulation, almost
80% of all produced neutrons escape from the QUINTA
target without any further interaction in uranium. There-
fore, the basic principles of the relativistic nuclear tech-
nology must be verified in the experiments with a large,
quasi-infinite spallation target with the minimal neutron
leakage. Such experiment will be carried out at Dubna
in the near future using the quasi-infinite uranium target
BURAN.
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Article received 21.02.2020
ЭКСПЕРИМЕНТАЛЬНЫЕ ИССЛЕДОВАНИЯ ЯДЕРНО-ФИЗИЧЕСКИХ ХАРАКТЕРИСТИК ПРОТЯЖЕННОЙ
УРАНОВОЙ МИШЕНИ, ОБЛУЧАЕМОЙ РЕЛЯТИВИСТСКИМИ ПРОТОНАМИ, ДЕЙТРОНАМИ И ЯДРАМИ 12C
А.А. Жадан, В.В. Сотников, В.А. Воронко, А.А. Балдин, С.И. Тютюнников, О.В. Бухал, К.В. Гусак, И.В. Жук,
П. Живков
В 2011-2017 гг. в рамках Международной коллаборации «Энергия и трансмутация РАО» была проведена серия экс-
периментальных исследований на глубоко подкритической урановой сборке «КВИНТА». Массивная урановая мишень
(512 кг natU) сборки облучалась 0,66 ГэВ протонами, дейтронами и ядрами 12С (1…4 ГэВ/нукл.) от ускорителей Фазотрон
и Нуклотрон (ОИЯИ, г. Дубна). Представлены основные результаты экспериментальных исследований, выполненных
при участии харьковской группы коллаборации.
ЕКСПЕРИМЕНТАЛЬНІ ДОСЛІДЖЕННЯ ЯДЕРНО-ФІЗИЧНИХ ХАРАКТЕРИСТИК ПРОТЯЖНОЇ УРАНОВОЇ
МІШЕНІ, ОПРОМІНЮВАНОЇ РЕЛЯТИВІСТСЬКИМИ ПРОТОНАМИ, ДЕЙТРОНАМИ ТА ЯДРАМИ 12C
А.О. Жадан, В.В. Сотников, В.О. Воронко, А.О. Балдін, С.І. Тютюнников, О.В. Бухал, К.В. Гусак, І.В. Жук,
П. Живков
У 2011-2017 рр. у рамках Міжнародної колаборації «Енергія і трансмутація РАВ» було проведено серію експеримен-
тальних досліджень на глибоко підкритичній урановій збірці «КВІНТА». Масивна уранова мішень (512 кг natU) збірки
опромінювалася 0,66 ГеВ протонами, дейтронами і ядрами 12С (1…4 ГеВ/нукл.) від прискорювачів Фазотрон і Нуклот-
рон (ОІЯД, м. Дубна). Наведено основні результати експериментальних досліджень, які було виконано за участю харків-
ської групи колаборації.
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