Purification of rare earth elements from thorium, uranium, and radioactive isotopes
This article presents the results of industrial tests of the technology of sorption, precipitation and extraction purification of the concentrate of rare earth elements (REE) from radioactive decay products of the uranium and thorium series. It has been shown that the combination of sorption, select...
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| Zitieren: | Purification of rare earth elements from thorium, uranium, and radioactive isotopes / A.P. Mukhachev, D.A. Yelatontsev, O.A. Kharytonova // Problems of Atomic Science and Technology. — 2021. — № 2. — С. 95-99. — Бібліогр.: 11 назв. — англ. |
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| author | Mukhachev, A.P. Yelatontsev, D.A. Kharytonova, O.A. |
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| citation_txt | Purification of rare earth elements from thorium, uranium, and radioactive isotopes / A.P. Mukhachev, D.A. Yelatontsev, O.A. Kharytonova // Problems of Atomic Science and Technology. — 2021. — № 2. — С. 95-99. — Бібліогр.: 11 назв. — англ. |
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| description | This article presents the results of industrial tests of the technology of sorption, precipitation and extraction purification of the concentrate of rare earth elements (REE) from radioactive decay products of the uranium and thorium series. It has been shown that the combination of sorption, selective precipitation, and extraction processes makes it possible to effectively purify REE from U, Th, Po, Ra, RaD, and Ac and to obtain radiation-safe nitrogencontaining solutions for the production of fertilizers and individual REE.
Викладено результати промислових випробувань технології сорбційної, осаджувальної і екстракційної очисток концентрату рідкісноземельних елементів (РЗЕ) від радіоактивних продуктів розпаду уранового та торієвого рядів. Показано, що поєднання процесів сорбції, виборчого осадження та екстракції дозволяє ефективно очищати РЗЕ від U, Th, Po, Ra, RaD і Ac і отримувати радіаційно безпечні розчини, які містять азот, для виробництва добрив та індивідуальних РЗЕ.
Изложены результаты промышленных испытаний технологии сорбционной, осадительной и экстракционной очисток концентрата редкоземельных элементов (РЗЭ) от радиоактивных продуктов распада уранового и ториевого рядов. Показано, что сочетание процессов сорбции, избирательного осаждения и экстракции позволяет эффективно очищать РЗЭ от U, Th, Po, Ra, RaD и Ac и получать радиационно безопасные азотосодержащие растворы для производства удобрений и индивидуальных РЗЭ.
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ISSN 1562-6016. ВАНТ. 2021. №2(132) 95
https://doi.org/10.46813/2021-132-095
UDC 546.65
PURIFICATION OF RARE EARTH ELEMENTS FROM THORIUM,
URANIUM, AND RADIOACTIVE ISOTOPES
A.P. Mukhachev
1
, D.A. Yelatontsev
2
, O.A. Kharytonova
2
1
Dnieper Institute of Geotechnical Mechanics, Dnipro, Ukraine;
2
Dniprovsk State Technical University, Kamyanske, Ukraine
E-mail: eah@ukr.net
This article presents the results of industrial tests of the technology of sorption, precipitation and extraction
purification of the concentrate of rare earth elements (REE) from radioactive decay products of the uranium and
thorium series. It has been shown that the combination of sorption, selective precipitation, and extraction processes
makes it possible to effectively purify REE from U, Th, Po, Ra, RaD, and Ac and to obtain radiation-safe nitrogen-
containing solutions for the production of fertilizers and individual REE.
INTRODUCTION
Uranium and rare earth elements (REE), gadolinium,
dysprosium, and europium are an integral part of the
fuel for nuclear reactors. The main source of the
medium-heavy fraction of REE until 1991 was the
Melovoe deposit (Kazakhstan). The concentrate mined
there was distinguished by a unique composition: along
with uranium (0.2%) and phosphorus (20%), the yttrium
content reached 18%, the sum of gadolinium and
dysprosium – 35%; europium – 0.8% [1, 2].
In force until 1991 capacities for the processing of
phosphorites, the production of uranium and phosphorus
fertilizers in Ukraine are mothballed due to the lack of
raw materials. Currently, the only explored deposit of
complex phosphorite ores in Ukraine, containing
uranium, thorium and REE, is the Novopoltavskoe
deposit in the Zaporizhzhia region [3]. When
implementing the State Program for the creation of
nuclear fuel, it can become the main source of
gadolinium, dysprosium and europium, with the
associated extraction of uranium and phosphorus.
A prerequisite for the production of REE is their
deep purification from impurities, incl. from uranium
and thorium, as well as from radioactive products of
their decay (Ra, Po, Pb, Ac). The processing technology
of uranium-rare earth phosphate ores is complex,
multistage, fine technologies of sorption and extraction
are used at the final stages of processing.
Phosphorites are atypical uranium-containing raw
materials, which contain Р2О5, uranium, REE, as well as
scandium and thorium [4, 5]. The associated extraction
of phosphorus, in the form of phosphorus fertilizers,
significantly reduces the cost of uranium and REE. In
the production of uranium and REE, as well as for the
nuclear power industry in general, the main issue is the
radiation safety of personnel and the protection of the
environment from radioactive contamination. This
becomes especially important when reprocessing
radioactive spent nuclear fuel (SNF), which contains
fissile isotopes of uranium and other elements. Effective
reprocessing of SNF to separate uranium and plutonium
is possible only with the use of chemical technologies
that are well mastered by the nuclear industry.
The work aims to present the results of industrial
tests of the technology for the purification of REE
concentrate obtained during the processing of phosphate
compounds and the extraction of uranium from
radioactive elements to the level of sanitary standards of
Ukraine.
RESEARCH METHODS
To select the methods for separating U, P2O5, REE
and purifying them from radioactive impurities, a
chemical analysis of the REE concentrate after the
extraction of uranium was carried out. To separate the
REE and the phosphate ion, the process of sorption of
the REE raffinate on the KU-2-8 cation exchanger with
an NHO3 content of 50…100 g/dm
3
was chosen. The
raffinate after sorption, containing phosphorus and other
non-radioactive elements, corresponded to the 97
Radiation Safety Standards for Ukraine (the NRBU-97)
according standards and was sent to obtain nitrogen-
phosphorus fertilizer of the “Nitrofos” type. To achieve
the maximum capacity of KU-2-8 for REE and
radioactive elements, the extraction raffinate was
diluted with a solution obtained as a result of washing
the saturated resin before sorption. In the course of
sorption, the optimal P2O5: REE ratio was determined,
at which their separation was the most complete.
Saturated cation exchanger, after washing to remove F
–
and PO4
3–
ions, was subjected to desorption with a
mixture of HNO3 and NH4NO3. In the process of
sorption, the capacity of the cation exchanger, the
kinetics of the process, and the residual content of REE
in the raffinate were determined.
After desorption, the residual capacity of the cation
exchanger, the elemental composition of the eluate, incl.
content of Th, U, Po, Ra, Ac, Pb. For desorption, a
regenerating solution with an optimal ratio of
HNO3:NH4NO3 was selected. Iron-thorium cake was
precipitated from the eluate with ammonia at pH = 4.0.
To extract REE, the cake was repulped with water at
S:L = 1:4 and a temperature of 65 °C.
The filtrate was sent to wash the saturated cation
exchanger. The eluate, after separation of Fe-Th cake,
was sent to the precipitation of REE hydroxides at
pH = 8.0…9.0. The precipitate of REE hydroxides was
dissolved in 45% HNO3 at an excess acidity of
mailto:eah@ukr.net
96 ISSN 1562-6016. ВАНТ. 2021. №2(132)
20…40 g/dm
3
. H2O2 was introduced into the solution to
convert Ce
4+
to Ce
3+
, to separate it during extraction,
after which it was sent for sulfide purification from
radioactive elements. For this, the salts Ba(NO3)2,
Pb(NO3)2, Na2S, and K4[Fe(CN)6] were used. The
released H2S was absorbed by a soda solution and sent
to the preparation of a 10% Na2S solution.
The precipitated radioactive impurities (Ra, Po,
RaD) and uranium were sent together with Fe-Th cake
for repulpation, and after washing with REE – for
disposal. The REE solution was analyzed for the content
of Po, Ra, Ac, and NH4NO3 was sent for purification
from
227
Ac by extraction using tributyl phosphate
(TBP). During the tests, the following was determined:
the ratio of the volumes of the organic and aqueous
phases (О:A) at all stages; the content of REE and
227
Ac
in the extractant and extraction raffinates; the content of
radioactive impurities. Residual radioactivity in
products, according to OSP-72/87 supplied to the
national economy, should not exceed 0.01% of
equilibrium thorium and uranium or 10
-10
Ci/g for the
sum of the following elements:
228
Ra,
228
Th,
234
U,
230
U,
226
Ra,
210
Pb,
210
Po,
227
Ac.
For the rapid determination of the
227
Ac content in
the REE, an improved method was used [6, 7], within
which the intensity of the γ-radiation from the
accumulated daughter elements of the actinium series in
the calcined REE residue was measured.
RESULT AND DISCUSSION
The processes of sorption and desorption of REE on
the KU-2-8 cation exchanger are described by the
equations [8]:
TR(NO)3 + 3RSO3H → TR(RSO3)3 + 3HNO3, (1)
TR(RSO3)3 + 3HNO3 → 3RSO3H + TR(NO)3, (2)
CH2 CH CH2
SO3H
where R =
.
The PO4
3–
and NO3
–
anions are not sorbed by the
resin. During sorption, the concentration of H
+
ions in
the solution increases. The kinetics of the process
provides a sorption duration of no more than 20 min.
The completeness of the REE sorption, within the
excess HNO3 content of 70…100 g/dm
3
, does not
depend on acidity. At the same time, at acidity less than
40 g/dm
3
of HNO3, the precipitation of REE phosphate
occurs, which leads to their losses [9].
It was determined that the solution for sorption
should have the following composition, g/dm
3
: REE –
20…25; the ratio P2O5:REE ≤ 2. The capacity of
KU-2-8 in such conditions was, kg/t: REE – 40…60;
Fe2O3 – 40; CaO – 25. The ratio of flows of resin and
solution was maintained at a level of 1:4. The raffinate
after extraction separation of uranium and REE
contained, g/dm
3
: REE – 19…25; U ≤ 0.01; P2O5 –
35…50; HNO3 – 100…150; Fe2O3 – 9…14; CaO < 35;
F < 0.01; Th – 0.1…0.3. In terms of the content of
radioactive elements, the raffinate did not meet the NRB
standards.
Desorption was carried out at a ratio of resin and
regenerating solution flows of 1:2. The composition of
the eluate after desorption, g/dm
3
: REE – 12; P2O5 –
2.0; Fe2O3 – 2.5; Al – 3.0; Th – 0.1; U – 0.02. The
completeness of the desorption process reached 100%.
The REE eluate containing radioactive isotopes was
sent to the precipitation of thorium and iron hydroxides
at pH = 3.5…4.5 and a temperature of 70 °С according
to the reactions:
Al, Fe(NO3)3+3NH4OH→Al,Fe(OH)3↓+3NH4NO3, (3)
Th(NO3)4+4NH4OH→Th(OH)4↓+4NH4NO3. (4)
To intensify the process of filtration of hydroxides, a
flocculant polyacrylamide (PAA) is added in the form
of a 0.1% solution. Repulpation of Fe-Th cake allows
reducing the loss of REE by 4 times. The technological
scheme for the purification of REE from phosphorus
and thorium is shown in Fig. 1.
Fig. 1. Technological scheme for the separation of impurities from REE
Raffinate after uranium
extraction
Making the pulp
Р2О5:REE = 2:1; H+ 80 g/dm3
Sorption of the REE and
radionuclides
45% HNO3
Raffinate for the
fertilizer production
Rinsing of the saturated
resin
Solution
H2O
Desorption
HNO3+NH4NO3
Precipitation of the Fe,Th-
cake and U at рН=3,5–4,5
NH3
K4[Fe(CN)6]
Filtration
REE-solution for the
sulphide treatment
Repulpation of
Fe,Th,U-sediment
Fe,Th,U-cake for disposalH2О
Filtration
Cake REE-filtrate for the
washing of KU-2-8
KU-2-8
0,1% PАА
ISSN 1562-6016. ВАНТ. 2021. №2(132) 97
The precipitation of the REE concentrate is
described by the reaction:
TR(NO3)3 + 3NH4OH → TR(OH)3↓ + 3NH4NO3. (5)
Chemical composition of REE hydroxides, %:
REE ≥ 90; CaO ≤ 4.0; Fe2O3 ≤ 0.5; P2O5 ≤ 1.0; Th+U ≤
≤ 0.2. The dissolution of the REE concentrate with
nitric acid occurs according to the reaction:
TR(OH)3 + 3HNO3 → TR(NO3)3 + 3H2O. (6)
Nitrate solutions of REE are an oxidizing agent, and
the used precipitant (Na2S) is a strong reducing agent.
Under reducing conditions, with an excess of H2S, the
isotopes of lead and polonium will be retained in the
sediment [10]. In the absence of an excess of Н2S, the
decomposition of the sulfide precipitate and the
transition of lead and polonium isotopes into the
solution will take place. The solubility of PbS depends
on the pH of the solution, therefore, during sulfide
purification, it is required to conduct the process in a
certain range of pH values. Sodium sulfide (Na2S) at
pH = 2.5…2.8 almost completely transforms into H2S
by the reaction:
2HNO3 + Na2S → H2S↑ + 2NaNO3. (7)
This phenomenon is undesirable; therefore, constant
pH control is required for complete precipitation of lead
and polonium sulfides. The transition of lead and
polonium into solution is observed only when the values
of the redox potential change from negative values to
positive ones, relative to the silver chloride electrode
[11]. The completeness of uranium deposition is
achieved by adding K4[Fe(CN)6] according to the
reaction:
UO2(NO3)2+K4[Fe(CN)6]→K2(UO2)[Fe(CN)6]↓+
+2KNO3. (8)
During the deposition of lead by the reaction:
Pb(NO3)2+Na2S→PbS↓+2NaNO3 . (9)
The pH rises to 0.7 and the ORP should not exceed –
60 mV.
226
Ra precipitated from solution in the form of
sulfate together with BaSO4 according to the reactions:
Ra(NO3)2+(NH4)2SO4→RaSO4↓+2NH4NO3 , (10)
Ba(NO3)2+(NH4)2SO4→BaSO4↓+2NH4NO3 . (11)
Together with Ba(NO3)2, Pb(NO3)2 is introduced,
which is a polonium co-precipitator. In the course of the
experiment, the optimal consumption of reagents was
determined, which was (per 100 kg of REE), kg:
Ba(NO3)2 – 0.5; K4[Fe(CN)6] – 0.13; Na2S – 0.5; H2SO4
– 0.4; Pb(NO3)2 – 0.24.
The precipitation of Fe-Th cake and sulfide
purification of the REE concentrate do not provide
purification from
227
Ac, a daughter product of the
radioactive decay of uranium, since this element is
similar in chemical properties to lanthanum. As a result,
anemones increase the total radioactivity of REEs when
they are divided into groups.
A solution after purification from radioactive
elements, containing REE nitrates in an amount of 100
and 200 g/dm
3
NH4NO3, as well as impurities, in terms
of the calcined product, %: Fe < 0.5; CaO < 4.0;
F < 1.5; Cl < 0.2; SO4 < 0.25; P2O5 < 1.0 has an
increased content of actinium – 50∙10
–10
Ci/g, at a rate
of 1∙10
–10
Ci/g.
In the course of the experiments, a technological
scheme for the purification of REE from uranium and
radioactive impurities, except for actinium, was
developed (Fig. 2).
Fig. 2. Technological scheme for cleaning REE from uranium and radioactive elements
REE filtrate after separation
of Fe-Th cake
Precipitation of REE
pH=9,0; 70 °C
Filtration
NH4NO3 230 g/dm3; РЗЭ 0,5 g/dm3
Dissolution of REE
Нexc. g/dm3
Conversion Се
4+
into Се
3+
REE g/dm3
HNO3
(NH4)2СO3
PАА NH3
H2O2
Removal of Ra, U
75 °C; 1 h
K4[Fe(СN)6]
H2SO4 Ba(NO3)2
Pb(NO3)2
Neutralization
рН=2,5–2,
NH3
10% Na2S
Filtration
Filtrate
REE g/dm3
NH4NO3 g/dm3
Ra,Po,U-sediment for
repulpation together with
Fe-Th cake
Extractive
Removal of Ac
REE 0.5 g/dm3
Neutralization
pH=2.5…2.
98 ISSN 1562-6016. ВАНТ. 2021. №2(132)
After separation of Th, Po, Ra, Pb, the REE filtrate
was sent for extraction purification from
227
Ac. The
REE extraction process using TBP is described by the
equation:
TR(NO3)3+TBP∙HNO3→TBP∙TR(NO3)3+HNO3 . (12)
The efficiency of the process depends on the
concentration of REE in the solution, as well as the
presence of a salting-out agent – the NH4NO3 salt. The
efficiency criterion is the composition of the regenerate,
which must contain the minimum amount of REE and
the maximum possible amount of non-radioactive
impurities and
227
Ac, so as not to return it to the cycle.
During the experiments, it was determined that an
increase in the concentration of REE to 300 g/dm
3
and
NH4NO3 to 400 g/dm
3
promotes an increase in the
extraction of REE and purification of the concentrate
from
227
Ac to sanitary standards.
The purified REE concentrate before separation into
groups contained
210
Po 10
–11
…10
–12
Ci/g and
226
Ra
10
–10
…10
–11
Ci/g, which meets the requirements of
NRB. The
227
Ac content determines the radioactivity at
the level of 10
–11
Ci/g, while the analysis duration
according to the new method [6, 7] was 5 days instead
of 15 according to the standard one. This significantly
reduces the cost of products.
As a result of industrial tests, a technological scheme
for the purification of REE from actinium was
developed (Fig. 3).
Fig. 3. Technological scheme for the extraction of REE from actinium
The proposed composition of the flow ratios at the
stages of extraction, washing, and stripping made it
possible to increase the extraction of REE up to 93%.
CONCLUSION
1. The release of thorium and iron hydroxides at
pH = 4.0 ensures the release of thorium from the
solution to the level of sanitary standards.
2. The use of Na2S and Pb(NO3)2 gives positive
results in the purification from the radioactive isotope
210
Po, and the use of K4[Fe(CN)6] makes it possible to
achieve almost complete separation of uranium.
3. The rational sequence of the introduction of
reagents (2% Pb(NO3)2, 5…10% Na2S) made it possible
to ensure the purification of the radioactive isotope
226
Ra to the sanitary standards.
4. A prerequisite for the purification of REE from
226
Ra is the introduction of the SO4
2–
ion in the form of
H2SO4 or (NH4)2SO4.
5. The process of extraction purification of REE
from the radioactive isotope
227
Ac allows to reduce its
content to sanitary standards (4∙10
–11
Ci/g) and obtain a
lanthanum concentrate with a purity of 99.88%. In this
case, the extraction of REE into the purified solution is
93%.
6. The combination of the proposed methods for the
isolation of radioactive isotopes ensures the safe work
of personnel during the separation of the REE
concentrate. The results of the study make it possible to
use the considered technological methods for SNF
reprocessing.
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Initial solution
REE 300 g/dm3; NH4NO3 400 g/dm3
HNO3 30 g/dm3; Ас 3∙10–9 Ci/g
Extraction
О:A = 2:1; n = 10
Raffinate
REE 3,5 g/dm3; Ас 1∙10–7 Ci/g
CaO 37%; SO4 18,9%
F 7,1%; Fe2O3 2,1%
Saturated organic phase
REE 150 g/dm3; Ас 4,4 –9 Ci/g
Washing
О:A = 5:1; n = 20
Organic phase
Ас 4,2∙10–11 Ci/g
Re-extraction
О:A = 2:1; n = 15
Evaporation
n = 3–3,5
Re-extract
REE 100 g/dm3; Ас 5,3 –12 Ci/g
5% HNO3
(75%) Separation REE
(2
5
%
)
R
e
-e
x
tr
ac
t
R
E
E
3
5
0
g
/d
m
3
T
h
e
w
as
h
in
g
s
o
lu
ti
o
n
R
E
E
3
5
0
g
/d
m
3
ISSN 1562-6016. ВАНТ. 2021. №2(132) 99
6. И.Е. Старик, Е.Е. Щепотьева. Методы опре-
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Ac. Заявка на а.с. СССР 014069 30.01.1969.
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Статья поступила в редакцию 20.11.2020 г.
ОЧИСТКА КОНЦЕНТРАТА РЗЭ ОТ ТОРИЯ, УРАНА И РАДИОАКТИВНЫХ ПРИМЕСЕЙ
А.П. Мухачев, Д.А. Елатонцев, Е.А. Харитонова
Изложены результаты промышленных испытаний технологии сорбционной, осадительной и
экстракционной очисток концентрата редкоземельных элементов (РЗЭ) от радиоактивных продуктов
распада уранового и ториевого рядов. Показано, что сочетание процессов сорбции, избирательного
осаждения и экстракции позволяет эффективно очищать РЗЭ от U, Th, Po, Ra, RaD и Ac и получать
радиационно безопасные азотосодержащие растворы для производства удобрений и индивидуальных РЗЭ.
ОЧИЩЕННЯ КОНЦЕНТРАТУ РЗЕ ВІД ТОРІЮ, УРАНУ І РАДІОАКТИВНИХ ДОМІШОК
А.П. Мухачов, Д.О. Єлатонцев, О.А. Харитонова
Викладено результати промислових випробувань технології сорбційної, осаджувальної і екстракційної
очисток концентрату рідкісноземельних елементів (РЗЕ) від радіоактивних продуктів розпаду уранового та
торієвого рядів. Показано, що поєднання процесів сорбції, виборчого осадження та екстракції дозволяє
ефективно очищати РЗЕ від U, Th, Po, Ra, RaD і Ac і отримувати радіаційно безпечні розчини, які містять
азот, для виробництва добрив та індивідуальних РЗЕ.
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| id | nasplib_isofts_kiev_ua-123456789-194898 |
| institution | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| issn | 1562-6016 |
| language | English |
| last_indexed | 2025-12-07T15:29:11Z |
| publishDate | 2021 |
| publisher | Національний науковий центр «Харківський фізико-технічний інститут» НАН України |
| record_format | dspace |
| spelling | Mukhachev, A.P. Yelatontsev, D.A. Kharytonova, O.A. 2023-12-01T13:31:40Z 2023-12-01T13:31:40Z 2021 Purification of rare earth elements from thorium, uranium, and radioactive isotopes / A.P. Mukhachev, D.A. Yelatontsev, O.A. Kharytonova // Problems of Atomic Science and Technology. — 2021. — № 2. — С. 95-99. — Бібліогр.: 11 назв. — англ. 1562-6016 DOI: https://doi.org/10.46813/2021-132-095 https://nasplib.isofts.kiev.ua/handle/123456789/194898 546.65 This article presents the results of industrial tests of the technology of sorption, precipitation and extraction purification of the concentrate of rare earth elements (REE) from radioactive decay products of the uranium and thorium series. It has been shown that the combination of sorption, selective precipitation, and extraction processes makes it possible to effectively purify REE from U, Th, Po, Ra, RaD, and Ac and to obtain radiation-safe nitrogencontaining solutions for the production of fertilizers and individual REE. Викладено результати промислових випробувань технології сорбційної, осаджувальної і екстракційної очисток концентрату рідкісноземельних елементів (РЗЕ) від радіоактивних продуктів розпаду уранового та торієвого рядів. Показано, що поєднання процесів сорбції, виборчого осадження та екстракції дозволяє ефективно очищати РЗЕ від U, Th, Po, Ra, RaD і Ac і отримувати радіаційно безпечні розчини, які містять азот, для виробництва добрив та індивідуальних РЗЕ. Изложены результаты промышленных испытаний технологии сорбционной, осадительной и экстракционной очисток концентрата редкоземельных элементов (РЗЭ) от радиоактивных продуктов распада уранового и ториевого рядов. Показано, что сочетание процессов сорбции, избирательного осаждения и экстракции позволяет эффективно очищать РЗЭ от U, Th, Po, Ra, RaD и Ac и получать радиационно безопасные азотосодержащие растворы для производства удобрений и индивидуальных РЗЭ. en Національний науковий центр «Харківський фізико-технічний інститут» НАН України Вопросы атомной науки и техники Thermal and fast reactor materials Purification of rare earth elements from thorium, uranium, and radioactive isotopes Очищення концентрату РЗЕ від торію, урану і радіоактивних домішок Очистка концентрата РЗЭ от тория, урана и радиоактивных примесей Article published earlier |
| spellingShingle | Purification of rare earth elements from thorium, uranium, and radioactive isotopes Mukhachev, A.P. Yelatontsev, D.A. Kharytonova, O.A. Thermal and fast reactor materials |
| title | Purification of rare earth elements from thorium, uranium, and radioactive isotopes |
| title_alt | Очищення концентрату РЗЕ від торію, урану і радіоактивних домішок Очистка концентрата РЗЭ от тория, урана и радиоактивных примесей |
| title_full | Purification of rare earth elements from thorium, uranium, and radioactive isotopes |
| title_fullStr | Purification of rare earth elements from thorium, uranium, and radioactive isotopes |
| title_full_unstemmed | Purification of rare earth elements from thorium, uranium, and radioactive isotopes |
| title_short | Purification of rare earth elements from thorium, uranium, and radioactive isotopes |
| title_sort | purification of rare earth elements from thorium, uranium, and radioactive isotopes |
| topic | Thermal and fast reactor materials |
| topic_facet | Thermal and fast reactor materials |
| url | https://nasplib.isofts.kiev.ua/handle/123456789/194898 |
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