SCIENTIFIC ABSTRACT SHEVCHENKO. V.B. - SHEVCHENKO. V.F.

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• Collection: Scientific Abstracts
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• Document Creation Date: November 2, 2016
• Document Release Date: August 23, 2000
• Sequence Number: 12
• Publication Date: December 31, 1967
• Content Type: SCIENTIFIC ABSTRACT

-SHEVUENNO) V. B.19 POVIUSM) N. S. and SOLOVHIN) A. S.
"Some Features of Processing Irradiated Fuel Elements at the First Atomic
IM Power Station in the U.S.S.R."
paper to be presented at 2nd UN Intl. Conf, on the peaceful uses of Atomic
Energy, Geneva, 1 - 13 Sep 58.

Vo F 41KC)
78-1-41/43
AUTHORS: Shevchenko, V. B. Shilin, I. V. Solovkin, A. S.
TITLE: Extraction of Perchloric Acid and Uranyl Perchlorate With
Tributyl Phosphate (Ekstraktsiya khlornoy kisloty i perkh1orata
uranila tributilfosfatom)
PERIODICAL: Zhurnal Neorganicheskoy Khimiit 1958, Vol. 3, Nr 1, pp.225-230
(USSR)
ABSTRACT: It is generally maintained in literature that the perchlorate-
-ion has no inclination to form complexes with the elements
of the actinide series (reference 1). Perchloric acid and
itss)luble salts are therefore often used for thi*mintenance
of the ionic density rthen the investigation of the m tureof
the compounds existing in aqueous solutions is required
(e.g. extraction in tributyl phosphate). The transition of
HClO into the organic phase is usually neglected. The auth-
ors proved however (reference 4) that the value of the equi-
librium-constant of the reaction of RC10 4 with TBPh (Y, ) can
Card 1/4 be compared with that of HNO 3 with TBPh. The investigalion of

78-1-41/43
Extraction of Perchloric Acid and Uranyl Perchlorate With Tributyl Phosphate
K 'The test results are given in tables 1 to 3-
P, UO2(CIO4)*
They show above all that U(VL) is extracted to a considerable
extent from perchloric acid solutions by TBPh though the va-
lues of the coefficients of distribution here, with equal
other test conditions were muchomaller than with an extraction
from nitric acid solutions. Nevertheless uranium passes com-
pletely over into the organic phase (table 2) at high TBPh-
-concentrations in the organic phase, or when a salting out-
-salt is present in the aqueous phase (e.g. NaClO ) after a
single shaking. It became evident by further testi that the
graphical method of the determination of the composition of
the complex compound extracted by TBPh cannot be applied in
the case of perchloric acid solutions. Hence, it does not
follow that the mechanism of extraction of HC10 and of
UO 2(CIO ) differs substantially from that of tfie nitric
acid so1uhons by TBPh. It can apparently be expected that
HCIO and uranyl perchlorate pass over into the organic phase
WhicA contains TBPh, as solvents HC10 4_yTBPh and UO 2(CIO 4) 2
Card 3/4 -xTBPh. There are 1 figure, 3 tables, and 12 references,

78-1-41/43
.Extraction of Perchloric Acid and Uranyl Perchlorate With Tributyl Phosphate
8 of which are Slavic.
SUBMITTED: May 22, 1957
AVAILABLE: Library of Congress
Card 4/4

sciv/76-3-6-36/48
The Zxtraction of Protactirlium by Leans of Alk.-l Plaos-phoric Acids
ASSOCIATIOU: Khimiko-tekhnologicheskiy institut in. D. I. Mendel,3yeva
(Chejtical-Technol,--6ical Institute imeni D. I. Mendeleyev)
5U3i-,ITT---D: December 3, 11057
Card 2/2

AUTHORS: Mikhaylov, V. A., Shevchenko, V. B., SOV/78-3-8-37/48
Kolganov, V. A. r----------- - -
TITLE: Investigation of the Extraction of Protactinium by Mono-and
Diisoamyl Phosphoric Acids (Issledovaniye ekstraktsii
protaktiniya mono- i diizoamilfosfornoy kislotami)
PERIODICAL: Zhurnal neorganicheskoy khimii, 1958, Vol. 3, Nr 8, pp. 1959-
1964 (USSR)
ABSTRACT: In the present paper the results of detailed investigations on
the extraction of protactinium by mono- and diisoamyl phos-
phoric acid from nitric acid solutions are given. The dependence
of the extraction of protactinium by mono- and diis3amyl phos-
phoric acid on the concentration of the extractive and the con-
centration of H+ and NOA- in the aqueous phase were investigated.
It is shown that in the extraction with dialkyl phosphoric acid
the distribution coefficient of protactinium is proportional to
the square of the concentration of the extractive in the organic
phase. The concentration of nitric acid ions is of no importance
in the extraction of protactinium. From the experimental re-
Card 1/2 sults may be concluded that in the extraction of protactinium

SOV/78-3-8-37/46
Investigation of the Extraction of Protactinium by Mono- and Diisoam-yl Phos-
phoric Acids
with isoamy! phosphoric acid-the extractive is at the same time
a complex former in aqueous phase. The probable mechanism of the
extraction of protactinium with isoamyl phosphoric acid under
the formation of highly hydrolizable complex compounds between
protactinium and extractive in the aqueous phase, and the
transition from protactinium in organic phase in form of PaK 5
were suggested (iscamyl phosphoric acid is called HK)
There are 3 figures, 4 tables, and 9 references, 3 of which are
Soviet.
ASSOCIATION: Khimiko--tekhnologicheskiy institut im. D. I. Mendeleyeva
(Chemical and Technological Institute imeni D. I. Mendeleyev)
SUBMITTED: December 9, 1957
Card 2/2

SOV/78-3-8-36/48
AUTHORS: Shevchenk6. V. B., SolovIcin, A. S., Shilin, I. V.
TITLE: About the Extraction of the Uranyl Perchlorate by Means of
Tributyl Phos,)h-,-te (K ekstraktsii perkhlorata uranila tri-
butilfosfatoia)
PERIODICAL: Zhurnal neorcrznicheskoy khimii, 1958, Vol. 3, Nr. 3, op. 1965-
1967 (USSR)
ABSTRACT: The distribution of uranyl perchlorate between water and a
solution of 1,2 mol. of tributyl phosphate (TBP) in M 4 was
studied as a function of the concentration of the salt in
aqueous solution (Table 1). It was shown that K PuO 2(Clo 4)2
increases -ivith a rise of the uranyl concentration in the so-
lution.When uranyl perchlorate is extracted by means of tri-
butyl phosphate an increase of the water contents occurs in
the organic phase. In virtue of the experiments it is assumed
that uranyl perchlorate is extracted bi tributyl phosphate in
the form of the following compound: UO 2(C'04)2 .2H20 .2TBP.
Card 1/2 There are 1 figure, I table, and 4 references, 2 of which are

SOV/78-3-6-36/48
About the Extraction of the Uranyl Perchlo.rate by Means of Tributyl Phosphate
Soviet.
SUBMITTED: February 2a, 195a
Card 2/2

SOV/78-3-9-16/38
AUTHORS: Shevchenko, V tskiy, N. S., Solovk-4r.,, A. S., Shilin,
hichkina: K. P., Tsvetkova, Z. N.
TITLE: The Extraction of Nitric Acid With Tributyl Phosphate
(Ekstraktsiya azotnoy kisloty v tributilfosfat)
PERIODICAL: Zhurnal neorganicheskoy khimii, 1958, Vol 3, Nr 9, pp 2109-2112
(USSR)
ABSTRACT: The distribution of nitric acid between the aqueous and the
organic phase containing tributyl phosphate in dependence on
the aqueous phase and the nature of the solvent of tributyl
phosphate was investigated. From the results may be concluded
that Kp considerably depends on the nature of the solvents of
tributyl phosphate. The influence of the nature of the solvents
on the distribution of nitric acid between water and tributyl
phosphate was investigated in the case of an ionic strength
of the solution of 1, 0,5 and 3. The maximum value of K p in
nitric acid solution with the ionic strength of 3 is obtained
if toluene is used as solvent for tributyl phosphate. The
Card 1/2 change of K p by the nature of the solvent in the case of an

SOV/78-3-9-16/38
The Extraction of Nitric Acid With Tributyl Phosphate
ionic strength of 3 is to be divided as follows: toluene,
benzene, kerosene) CCl 2F-CCl2F, CCl 4* The following variation
of the above sequence takes place if the ionic strength is
reduced to 1: kerosene, toluene, benzene, CCl 2F-CCI2F, Ccl 40
ComparatiVe investigations of the extractions in HC10 4 and
HNO3 solutions showed that the complex HC10 4% TBPh is to a
greater extent polar than the complex HNO 3* TBPh.
There are 2 figures, I table, and 9 referencess 4 of which,
are Soviet.
SUBMITTED: August 3, 1957
Card 2/2

SEVCENKO, V.B. (Shevchej*o,-V.B.Ij POVICKLI, N.S. (Povitakiy, N.S.1;
SOLOVk-iN,A.S.; KOHTUS, J. (translator)
I
- L
Some peculiarities in processing the burnt out fuel elements
from the first atomic power plant in the Soviet Union. Jaderna
energie 4 no.11:342-344 N 158.

(2) SOV/89-5--5-5/27
AUMORS: Shevchenko~ V. B., Smelov, V. S.
TITLE: The Influence of Mono- and Dibutyl Phosphates on the Separation
of Plutonium by Tributyl Phosphate (Vliyaniye mono- i di-
butilfosfatov na ekstraktsiyu plutoniya tributilfosfa-tom)
PERIODICAL: Atoninaya enerriya, 1958, Vol 5, Ur 5, P.-,) 542 -545 (USSR)
ABST11ACT: The distribution coefficients for mono- and dibutyl phoe-
phate (MBPh and DBPh) between the or--anic phase, which
contained tributyl phosphate in hydrated petroleum, and
water were determined. The same coefficients were also de-
termined between the organic phase and a solution of n2ric
acid, a lye, and a soda eolution. The experimentally determin-
ed coefficients are shown in form of a table and a graph.
The determination of the distribution of -lutonium was car-
ried out in glass cups. The time required for establishing
equilibrium was experimentally determined as amounting to
30 minutes, and settlingr time was found to be 24 hours. The
plutonium was found to be quadrivalent. Concentration:50 mg/1-
Card 1/3 The plutonium was detected with the aid of its a-radiation,

PHASE I BOOK EXPLOITATION SOV/5084
International Conference on the Peaceful Uses of Atomic Energy. 2d, Geneva, 1958.
Doklady sovetskikb ucbenykh. [t.41 Mximiya radioelementov i radiatsionzykh
prevrashcheniy (Reports of Soviet Scientists. v. 4.: Chemistry of Radio-
elements and Fadiation Transformations) Moscov, Atomizdat, 1959. 323 P.
8,000 copies printed. (Series; Its: Trudy)
Ed. (Title page): A. P. Vinogradov, Academician; Ed.: V. I. IAbazaov; Tech. Ed.:
Ye. I. Mazell.
PURPOSE: This collection of articles is intended for scientists and engineers
interested in the applications of radioactive materials in science and
industry.
COVEPAGE: The book contains 26 separate studies concerning various aspects of
the chemistry of certain radioactive elements and the proceBses of radiation
effect on matter. These reports discuss present-day methods of reprocessing
irradiated nuclear fuel, research in the chemistry of mercury, thorium,
uranium, plutonium, and americium, problems related to the sorption and bury-

Reports of Soviet (Cont.)
smI04
ing of radioactive wastes,, the radiolysis of aqueous solutions and of
organic compounds, the mechanism of polymer chain grafting, and the effect
of radiation on natural and synthetic'rubbers. V. N. Prusakov edited the
present volume. Most of thereports are accompanied by references. Con-
tributors to individual investigations are mentioned in annotAitions to
the Table of Contents.
TAME OF COWBNTS:
Vinogradov, A. P. Meteorites and the Earth's Crust (The Geochemistry of
Isotopes) Ohport No. 2523)
8hevchenko,_Y_-_j4J, H. S. Povitakiy, and A. S. Solovkin. Some Special
Problems in the Reprocessing of Irradiated Heat-Producing Elements of the
FIrst Atomic Electric Power Plant of the USM (neport No. 2182) 28
[The following personalities are mentioned as having taken part in
this investigation: Z. M. Indi ov, K. P. Lunichkin , Ye. V. Ukraintsev,
Z. N. Tsvetkova, and V. V. Chubukov.)
Vdovenko, V. M., and M. P. Novallsk". Separation of Uranium and Pluto-
nium From Fission Products by Axtraction With a YAxture of Dibutyl Ether
and Carbon Tetrachloride (Report No. 2216) 34
Card-2/4

Reports of Soviet (Cont.)
SOV/5084
Vdovenko, V. M. Distribution of Fragmentation Elements in the Process
of the Ether Extraction of Uranium and Plutonium (Report No. 22o6) 41
P.rusakov, V. N., N. F. SimonovIand N. M. Trotseako. Dry Method of Re-
generating Irradiated Uranium (Report No. 2253) 49
[The authors thank I. K. Kikoin and A. T. Kolotukhin.']
Brezhaeva, N. Ye., V. I. Levin, G. V. Korpusov, N. M; Man1ko, Ye. K.
Bogacheval L. T. Khoreshko, and G. F. Platnova. Separation of Fragment-
ation RELdioactive Elements (Report No. 2295) 57
[The authors thank S. Z. Roginskiy, Corresponding Member AS USSR.]
Byabehikov, D. I., M. M. Senyavin, and Yu. S. Sklyarenko. Separation of
Individual Foxe Earth Elements (Report No. 2231) 75
Nikol'skiy, B. P., and V. I. P&ramonova. Using Ion-Exchange to Study the
State of RadioactiVe-Substances in Solution (Report No. 2204) 89
Card--5/-g

9 U-~ i'M t, Z_=
54 -.3 s
14
Ilia
JL 114
. !A.
1.3 all i

-SHEVCHEW, I?R.; SOLOVXXN. A.S,; SHILIN, I.Y.; KIRILWY, L.A.; RODIONOV#
A:.'V'.; BALUMINA, V.V.
,.v
3
11pat of the nature of the diluent on the extraction of uranyl
nitrate by tributylphosphate. Radiokhimlia I no-3:257-269
159. (MIRA 12:10)
(Urarvl nitrate) (Butyl phosphate)

21(l)
AUTHORS: Shevchenko V B Smelov, V. S. SOV/89-6-2-5/28
TITLE: On the Mechanism of Plutonium Nitrate Extraction by Mono-
and Dibutylphosphatea (K voprosu o mekhanizme ekstraktsii
nitrata plutoniya mono- i dibutilfosfatami)
PERIODICAL: Atoqziaya energiya, 1959, Vol 6, Nr 2, PP 140 - 144 (USSR)
ABSTRACT: The mechanism of plutonium extraction by monobutylphosphate
(MBP) and dibutylphosphate (DBP) is explained. Furthermore
the mechanism of plutonium nitrate extraction by MBP and DBP
is investigated with an ionic concentration of 6. In paper
I the experiments are described inare in detail. The following
method of analysis was applied: -11fter the solution had settled
for 24 hours the plutonium content was determined by counting
the a-particles. Self-absorption was taken into account in
solutions containing much LiNO . There was an error of 5-7c/~
in the determination of the reKlts of two simultaneously
investigated samples. The analysis of MBP and DBP was carried
out according to the method mentioned in reference 1. MBP and
DBP were determined with an accuracy of 7-12%. The extraction
Card 1/4 process may be represented in the general form

On the Mechanism of Plutonium Nitrate Extraction by Mono- SOV/89-6-2-5/28
and Dibutylphosphates
[puRn] 4-n +[4_,,]HR # puR 4 + (4-n)H'~'
Liquid Organic Organic Liquid
Phase Phase Phase Phase
where R denotes either
CH(C4H9 )FO 41' or [(c4H9)2PO4] 1 and n may adopt the values 1,2.
3 and 4. Since the equilibrium concentration of plutonium
in the aqueous solution is.smaller than 2.1o-4 mol/l, the
formation of atomic compounds must be neglected. The equili-
brium constant of the above-mentioned reaction has the form:
4-n
Kp = CPuR4 Clr+
4-n 4-n
CFuR CHR
n
The indices denoting the phases are not mentioned here. The
plutonium distribution coefficient E may be determined according
to the equation:
Card 2/4

On the Mechanism of Plutonium Witrate Extraction by Mono- SOV/89-6-2-5/26
and Dibutylpho~phates
C PuR4
C4-n
PuR
Since the effect of ITO 3-ions on the plutonium distribution
coefficient is insignificant, the possibility of complex
formation was not taken into account. The presence of complex
compounds with the ions R I and ClTO31' and the ions R I and (OH]'
was not taken into account either. It was demonstrated in an
earlier paper that the de.Dendence of the plutonium distribution
coefficient on the MBP, DBP and H+ concentration may be re-
presented by a straight line with tga = 1. According to these
results the foroula introductorily mentioned may be expressed
as follows:
PuR+ + HR ;F=4- Pu R +
Card 3/4 3 4

On the Mechanism of Plutonium Nitrate Extraction by SOV/89-6-2-5/28
Mono- and Dibutylphosphates
Thus it is demonstrated that the complex formation in the
liquid phase is also due to the extracting agent. The equi-
librium constant of the int raction of plutonium nitrate
with IMP is (1.5 � 0.25).10 , and (6.15 � 0.85)-lo3 with DBP.
There are 5 figures, 4 tables, and 3 references, 2 of which
are Soviet.
SUBMITTED: MaY 7, 1958
Card 4/4

210), 5(2) SOV/89-6-4-5/27
AUTHORS: Shevchenko, V. B., Timoshev, V. G., Volkova, A. A.
TITLE: The Stability Constants of the Nitrate Complexes of Trivalent
Plutonium and Tributyl Phosphate Solutions (Konstanty ustoy-
chivosti nitratnykh kompleksov trekhvalentnogo plutoniya v
vodnykh i tributilfoafatnykh rastvorakh)
PERIODICAL: Atomnaya energiya, 1959, Vol 6, Nr 4, PP 426-430 (USSR)
ABSTRACT: The distribution of nitric acid and plutonium nitrate between
the aqueous phase and tributyl phosphate (TBF) dissolved in
benzene is measured. Extraction was carried out in calibrated
test tubes. Mixing of phases was carried out. mechanically. The
initial quantities for the aqueous and organic solutions were
5 ml. All chemicals were e.speoially purified before the exper-
iments. Thus, the water content of TBF was only 0.111i6. The
reduction of the Pu from the aqueous plutonium nitr-atbe solution
5.10- 4 11) and from hydrazine ni'rat6 (0.2 M) was carried
u
out at 50-600 in the course of 3-4 hours. 7~1-atonium valence
was measured and calculated respectively both spectrophoto-
metrically as also from the oonstancy oil the plutonium distri-
Card 1/2 bution coefficient at the various re(luction steps (from one

SOV/691-6-4-5/27
The Stability Constants of the Nitrate Complexes of Trivalent Plutonium
and Tributyl Pho-sphate Solutions
and the same aqueous solution.). The plutonium content in the
aqueous and organic phases was determined radiometrically.
Hydrazine concentration was measired by titration of the hy1ra-
zine solution with potassium pervan.-anate in a hydrochloric
acid medium in the presence of ammozaium 7anadate. It could
be shown that trivalent plutonium is axtracted from a
combined with nitric acid by TBF in form of Pu(NO 3)3* TBF (Pitra-
tion concentration up to 1.2 V). In the case of the aforemen-
tioned experimental conditions, the distribution coefficient
of trivalent plutonium does not depend on hydrogen ion concer-
tration. The measured values are given in tables and partly
in form of graphs. Good agreement was found between calculated
and measured distribution coeffi-,ior.+-_,. The stability constants
for various plutonium complexes were determined as follows:
PU(NO 3)3*3TBF 0.75� 0-10 9 PU(NO 3)3 14-4.� 0-8
Pu(NO 3)2+ 14-3 � 0-8 , Pu(NO3)2+ 5.9 � 0.5
There are 3 figures, 5 tables, and 14 references, 10 of which
are Soviet
SUBMITTED: May 16, 19;8
Card 2/2

50) SOV/89-7-3-6/29
AUTHORS, Shevchenko, V. B., Slepchenko, 1. G., Shmidt, V. S.;
Nenarokomov, E. A.
TITLE: Extraction Properties of Di-isoamyl Esther of Methyl Phosphoric
Acid
PERIODICAL: Atomnaya energiyat 1959, Vol 7, Nr 3, PP 236-243 (USSR)
ABSTRACT: By hithert6 known methods the distribution coefficients of
HNO3 and uranyl nitrate in solutions of nitric acid and solutiow
of DAMPA (di-isoamyl esther of methyl-phosphorfe acid) in
petroleum were determined on the basis of he DAMPA-cont-rnt
in the extractive and on the UO 2(N03)2 and HNO 3- content in the
aqueous phase. It could be shown that, especially in the
aqueous phase, small uranium concentrations can be extraoted
with DAMPA considerably better than with TBP (tributy! phosphate).
The extraction mechanism develops according to the equation
H+ + N03 + DAMP~k. z= HN.0, DAMPA (1
where HMO3DAJAPA is a compound extracted entirely from the ozganic
phase. The rules governing the extraction of uranlum from
Card 1/2 solutions containing nitric acid by DAMPA-solutions may be

SOV/89-7-3--6/29
Extraction Properties of Di-isoamyl Esther of Kethyl Phosphoric Acid
explained by the following extraction equation:
UO2 + 2N0 -+ 2DAMPA EU02(NO3)2 (DAMPAQ (2)
2 3
where 0 (NO is a compound extracted entirely
IU 2 3)2 (DAMPA 2
from the organic phase. The equilibrium constant of reaction W
by using 10- and 20% DAMPA-solutions is 0 30 + 0.03 (measured
value). The equilibrium constant of reaction T2) with a 20%
DAMPA-solution, however, is 2540 + 200. The values determined
during the various experimental stages are represented partly
by tables and partly graphically. Therie are 10 figures, 5 tables,
'and 20 references, 14 of which are Soviet.
SUBMITTED: December 11, 1958
Card 2/2

S/186/60/002/001/002/.022
A057/A129
AUTHORS: Shevchenko, V.B.; Fedorov, I.Ai
TITLE: Effect of the temperature on the extraction of uranyl-, plutonium-,
ruthenium-, and zirconium-nitrates with tributyl phosphate
PERIODICAL: Radiokhimiya, v. 2, no. 1, 1960, 6 - 12
TEXT: In the present paper an attempt was made to determine basic condi-
tions concerning the temperature effect on tributylphosphate (TBP) extraction of
uranyl-, plutonium-, ruthenium-, or zirconium-nitrate. Literature data regarding
this problem are incomplete or not systematic. Nevertheless the knowldge of the
temperature effect on extraction is important for the separation of uranium and
plutonium from fission products. The present experiments were carried out with
initial solutions of uranyl nitrate in concentrations ~f 0.01, 0.2 and M m,
while solutions with other elements contained just tracer amounts of these. The
tributylphosphate concentration varied from 0.3 to 3-67 M, using as diluent a
mixture of saturates hydrocarbons (boiling at 182 - 2220C). During the extrac-
tion the temperature was kept with an accuracy of t 0.10C at 5, 10, 20, 30, 40,
60, or 800C. Initial volumes of 10 - 20 ml were uged, equilibrium was reached in
Card 1/8

S/186/60/002/001/002/022
Effect of the temperature on the extraction of..-.. A057/A129
5 10 min, and the samples were allowed to stand for 30 - 40 min (with 3.67 M
TBP for several hours). The acidity of the initial solutions was determined by
potentiometry, uranium was determined by gravimetry (or colorimetryVith Na-di-
ethyl dithiocarbamate), while Zr, Ru, and Pu were determined by radiometry. The
distribution coefficient KP was calculated from the ratio (Co/Caq) of the concen-
tration in the organic and aqueous phase. Experimental data Fig. 1) demonstrate
that with increasing temperature the distribution coefficient for HN03 between
water and 1.43 M TBP decreases. By increasing HNO concentration a decrease in
the effect of the temperature on Kp can be observea. Thus an increase from 50C
to 800C decreases K twice for extractions from 0.5 N HN03 solutions, 1.7 times
for 1.72 N HN031 Q 1.3 times for 3 N HN03 solutions. Apparently, constancy of
K [observed by B. Weaver et al, Ref. 5: J. Am. Chem. Soc., 75, 16, 3943
&3H')'P with changing temperature is valid only for lower acidities (from 5 N
HN03). With Increasing concentration of uranyl nitrate in TBP the effect of tem-
perature on the extraction decreases. Thus Kp U02(NO3)2 for extraction of an in-
itial solution containing 0.21 M uranium in 1.7 HN03 is at 50C 2.1 times greater
than at 800C using 1.47 M TBP as extractant, while using 0.36 M TBP the value .
changes 1.6 times. Extractions from 0.01 M uranium solutions are even more sen-
sitive for changes in temperature. The curves for the dependence of log Kp on
Card 2,/8

3jIb6/60/002/Q-"Q02,'G22
Effect of the temperature on the-extraction_of._._.'_.___ A057/A129_____
I/T (Figs. 2, 3) demonstrate that the extraction of uranyl,nitrate with TBP occum
according to the Van't Hoff'equation. -The reaction is isothermal and controls
principally the decrease of the distribution coefficient' of uranium with temper-,
ature. The temperature effect of plutonium on extraction was investigated in
soi~utions containing and not containing uranium. The distribution coefficient of
Pu increases with temperature from 10 to 400C (Fig. 4) and drops.then'with a
further temperature increase. Solutions with affinitial HN03 concentration of
0.5 N (not contain'ing uranium) show that extractability of'Pu4 decreases contin-
uously with increasing temperature (Fig. 4, curve 1). 'The effect of acidity on
the change of the distribution coefficient with temperat:ure interval from 10 -
40-OC and is not so evident between 40 - 800C. The*present authors discuss state-
ments of some other nvestigators [Ref. 8: D.W. Okendi, J. Chem. Soc., 3358
(1956); Ref. 9: G. Seaborg, J.'Katz, Actinides, N.N.E.S.; Ref. 10.: H.H. Ander-
son, The Transuranium Ele~ents, 2, 964 (1949); Ref. 11: J.A. Brothers, '.'.
Hart, W.C. Mathers,-,. Inorg. Nucl. Chem., 7, 85 (1958)] concerning the state of
plutonium in solutiois and assure the following equilibrium in solutions with an
acidity'between 0.5 and 4 N H'NO3:
PU4+
PU(NO3)3+ Pu(NO,):+ -.Pu(N03)+
3
Pu(N03)4 PU(N03)j- Pu(NOO"_
J t
JU(NO.0s..,
Card 3/8
22hril

S/186/60/002/001/002/022--------
Effect of the tempgrature on the~-extraotion of...., A057/A129
With Increasing acidity the amount of Pu(NO3); increasis. Supposing the whole
equilibrium system is exothermfe (according to Ref. 12: R.E. Connick, W.H. McVey,
J. Am. Chem. Soc., 71, 3182 (1949) pu4 + NO~ --* Pu(No3)3+ is exothermic] the
present authors consider that the increasing number of nitrate groups in the plu-
tonium nitrate complex is an exothermic,process. The observed dependence of the
extractability of plutonium on the temperature could thus be explained 4y the ef-
fect of prinoiphlly two factors: 1) the shift of the equilibrium of Pu nitrate
complexes in aqueous solutions with increasing temperature, and 2) the exothermic
formation of the N(NO )4 , 2 TBP complexes, which can be extracted into the or-
ganic phase. In solut?ons with an acidity above 1.7 N HN03 the first factor pre-
vails until 400co while above 400C the second factor is predominant. The c9ntin-
uous decrease of K with increasing temperature in solutions with an acidity be-
p
low 0.5 N HN03 is to be explained 'by the summary effect of both factors. Extract-
ability of zirconium nitrate.-decreases with increasing temperature (Fig. 5) be-
tween 10 and-300C. Above 300C the extractabhity increases with temperature.'
The effect of temperature is more pronounced in solutions at lower HN03 concentra-
tion. Discussing the state of zirconium in the-present investigations the auth=
assume, based on observations in sulfate complexes of zirconium [Ref. 16: W.B.
Blumenthal, Ind. Eng. Chem., 46,'528 (1954)], that with increasing temperaturethe
Card 4/6

Eff.ect of the temperature on the extraction of.... Q9X%002/001/002/022.
equilibrium between nitrate and basic zirconium salts shifts towards the forma-
tion of the latter. Thus the amount of extractable nitrate complexes decreases
and accordingly also the extractability of zirconium. Increase in zirconium ex-
tractability above 300C can be explained by the effect of some other factors,
like an increase in the solubility of the zirconium solvate complex, and increas-
ing concentration of dibutyl phosphate. Extractability of ruthenium decreases
with increasing temperature (Fig. 6). Theexistence of the following equilibri-
um is assumed by D.M. Fletcher and F.S. Martin, Chemistry of Nuclear Fuels:
[RuNO(NO3)3(H20)214::a'[RuNO(NO3)20H(H20)21~--t[RuNO.(NO3)(OH)2(H20)2]. The trini-
trate complex is easily extractable. With increasing temperature equilibrium
shifts towards the formation of the difficultly extractable di- and mono-hydrate ly
complexes. Thus extractability of ruthenium decreases. The maintenance of def- 'A
inite temperature conditions in each step of the extraction process of nuclear
fuels can improve the separation of uranium and plutonium from fission products.
There are 6 figures and 18 references: 1 Soviet and 17 non-Soviet.
SUBMITTED: May 20, 1959
Card 5/13 -

SHEVCHINKO, V.B.- SUOVKIN, A.S.; SHILIR, I.V.; KM1LOT, L.Ne--, RODIONOT, A.T.-I
V.V.
Effect of h7drocarbons of the aliphatic and aromatic series on the
extraction of U(VI), Fu(IT), Zr(IV), and Ce(III) with tri-n-butyl-
phosphate from nitric acid solutions. Radiokhimiia 2 no-3:281-290
16o. (MIRA 13:10)
01~rdrocarbons) (Extraction (Chemistry-))
(Butyl phosphate)

PETROV, K.A.; SHMVCE3NKO T.B.- TD40SHEY, Y.G.; MAKLYAYBV. N.A.; IMIN,
A.V. ; iANDINL, V.V.; YNLIKIN&, A.V.; NAGNIBM,
t IW
Z.I.; VOLKOVA, A.A.
Alkyl phosphonates, dipbosphonates, and phosphine oxides as
extracting agents. Zhur.neorg.khim- 5 no.2:498-502
F 160. (MM 13:6)
(Phosphonic acid) (Phosphine oxide)
(lixtraction(Chomistry))

'r, -9aoo(A) 69013
AUTHORS: Denotkina, R. G., Moskvin, A. I., S/078/60/005/04/008/040
Shev henk-o.- V.-B. BOO4/BOO7
TITLE; The Solubility Product of Bisubstituted Plutonium(IV)Phosphate
and Its Solubility in Some Acids
PERIODICAL: Zhurnal neorganicheskoy khimii, 19609 Vol 5, Nr 4, PP 805 - 810
(USSR)
ABSTRACT: The authors investigated the solubility of Pu(HPO 4)2* XH20 in
HC104 and HNO 39 and determined the solubility product of this
compound. Solubility was determined at a constant ion strength - 29
which was maintained by addition of NaC10 4 or UNO Y The preoipi-
tation of Pu/HPO (x fluctuates according to the authors#
k 4)2'XH20
data between 1 and 4) was effected from a solution of
1 - 2 M Pu(IV)-nitrate by a solution of 0-4 X H 3 PO4. The experi-
mental data are given as follows: Figure I - influence of hydrogenion
concentration upon the solubility of Pu(HPO 4)20 xff20 in HNOV
figure 2 - the same in B010 4. Hydrogen ion concentration was mea-
Card 1/3 sured by means of an LP-5 potentiometer. The solubility of

The Solubility Product of Bisubstituted
Plutonium(IV)Phosphate and Its Solubility in
Some Acids
SUBMITTED:
69013
3/078/60/005/04/008/040
B004/BO07
the solubility of the Pu(IV)phosphate was determinedura5hi-
cally from experimental data for the solubility of IV phos-
phate in mixtures of HNO 3 and R3PO4 (Fig 3). The mean value
of the solubility product determined according to the three
methods is 2.10-28. A comparison between the solubility
product of Pu(IV)phosphate and the corresponding h- and
U-compounds shows that the Pa-compound has the lowest solubi-
lity, because of its lower ionic radius. There are 3 figureep
4 tables, and 6 referenceep 5 of which are Soviet.
December 18, 1958
Card 3/3

SHEVCHMO, V.B.; SLEPCEMO, I.G.; SM4IDT, V.S.-, NEN&ROKOMOV, B.A.
Mecbanism of extraction of uranium (VI) with tributyl phosphate
--afrom hydrochloric acid solutionB. Zhur.neorg.khim. 5 no.5.1
1095-1099 MT 160. (KM 13:7)
(Uranium) (Buty-1 phosphate)
(Extraction(Chemistry))

S/078/60/005/06/24/030
0 0 B004/BO14
AUTHORS: Shevchenko, V. B.9 Shilin, I. V.. Zhdanor, Yu. F.
TITLE: The Behavior of Copper Nitrate in the Extraction of the
Nitrates of Uranyl and Plutonium by Means of Solutions
of Tributyl Phosphate
PERIODICAL: Zhurnal neo.-ganicheskoy khimii, 1960, Vol- 59 No- 6,;
pp. 1366 - 1374 L-K
TEXT: The authors of the preseiit paper wanted to study the behavior of
large impurities of copRer (in addition to compounds of Ni9Cr,Fe0Co9
and Mo) in nuclear fuelmthat is regenerated by extraction by means of
benzene- or kerosene solutions of tributyl phosphate (TBP). The authors
write down the reaction equation (2) for the extraction of Cu(NO 3)29
and on the basis of the law of mass action they derive squation (3):
log Kd log X + X log[TBPI,,gg where K. - dietribution ratio of Cu(No 3)2
and K equilibrium constanto It follows from Table 1 and Fig. I that
Xd increases with rising concentration of TBP and increasing ionic
Card 1/3

The Behavior of Copper Nitrate in the Extran.-ition S/076 0/005/06/24/030
of the Nitrates of Uranyl and Plutonium by Means k04YB6014
of Solutions of Tributyl Phosphate
Strength p of the aqueous solution. Kd dropa, hows~ver, with constant ii,
constant concentration of TBP, and rising concentrat-ion of the copper
nitrate in the aqueous solution (Figs. 8 and 9). K. is higher in TBP-
kerosene solution than in TBP benzene (Table 2). It follows from Fig. 2
that by means of TBP benzsne copper nitrate is extra-)ted as
CU(NO 3)20 2TBP.H20, whereas it is extracted aq Cu(NO 3)2s3TBP.2H 20 b;r Lr
means of TBP kerosene. These compounds are only stable abo-Te -100C.
Fig- 3 shows the effect of HNO on K a 9 Fig- 4 the distribution of HNO~
3
among water and TBF in the presence of Cu(NO 3)2, Fig. 5 shows that Y-d
does not depend on the equilibrium concentration of the e ion. The
distribution ratio of copper nitrate ~.s lowered by "his presence of
uranyl nitrate (Table 3., Fig. 6) . whereaa alumiaum nit'rate raises K.,
(Fig- 7). Furthermore, the authors studied the solubility of copper
nitrate in TBP as well as the physical data of t~As solvent (Tables 4-6,
Fig. 10). TBP kerosene is divided into two layeis when it ie saturated
Card 2/3

The Behavior of copper Nitrate in the Extraction S/078/60/005/06/24/030
of the Nitrates of Uranyl and Plutonium by Means B004/BO14
of Solutions of Tributyl Phosphate
with copper nitrate (Table ~)* Hence, the solubility of TBP saturated,
with copper nitrate is limited in saturated hydro*arbons. There are
10 figures. 7 tables, and 14 references: 8 So-~iet, I American,
3 British, I German, and I Yugoslav.
SUBMITTED: February 26, 1959
Card 3/3

J,
940
S/07 66/005/07/05/014
B004rB(0,56
AUTHORSi Denotkina, R. G., Moskvin, A. I., Shevchenko, V. Be
TITLEs Determination of the Composition and4tbe Dissociation
Constants of the Phosphate Complexeslof Plutonium (IV) by
Means of the Solubility Methud q
PERIODICAL: Zhurnal neorganicheskoy khimii, 1960, Vol. 5, No. 7,
pp. 1509-1515
TE.XT3 In order to obtain stable solutions of nitric acid when dissolving
the fuel elements consisting of an uranium-molybdenum alloy of the first
atomic power plant of the 'USBRt 20-40 g1l phosphoric acid is added. This
caused the authors to investigate the complex-formation of plutonium (IV)
in solutions of phosphoric acid and to determine the ratio between metal
and addend and the dissociation constants of the complexes. They in-
vestigated the solubility of the gelatinous Pu(HPO 4)2.xH20 in 0.012 to
2 mole/l phosphoric acid in the presence of 2 M ENO 3 at 250C. The ex-
perimental data are shown in Table 1 and Fig. 1. The solubility of
Card 1/3

Determination of the Composition and the S/OrID/005/07/05/014
Dissociation Constants of the Phosphate ,6
0 a 0.
B004 B05
Complexes of Plutonium (IV) by Means of the Solubility Method
plutonium (IV)-phosphate at first decreases, attains a minimum at
1.06x.10-4 mole/l, after which it increases as a result of complex
formation. From the curve in Fig. I it may be seen that the number of
phosphate groups in the complex ion increases steplike from 1,2,3,4 to 5-
The following instability constants are calculated for [Pu(HPO A 2+
Knj = 1.2.10-13; for FPti(HPO )2]o K", . 1.6.10-24; for FPU(EPO )312-
C - 4 4
Kn,; - 3-7-10-34; for F~u (E[po4Q4- Kn - 6.10-44; and for Epu (HP04) 51 6-
-53 4
Kn 5- 9.10 . Fig. 2 shows the dependence of the exponent of the in-
stability constants an the ratio between metal and addend. When increas-
ing the hydrogen-ion concentrationg acidolysis of the phosphate com-
plexes occurs, also for which the constants are calculated. Further, the
solubility of the dry plutonium diphosphates in aqueous phosphoric acid
solution (0-03-3-9 mole/1) was investigated. The results are given in
Card 2/3

8 1
Determ'naltion of the Comuosition aiid the S/0 ~ 12 0/005/07/05/014
Dissociation Constants of the Phosphate BOONB056
Complexes of Plutonium (IV) by Means of the Solubility Method
Table 2 and in Fig. 3 - Complex ions with the ratio metal z addend - 1 : 3)
1 : 4, and 1 9 5 were found. Formation of these complexes could be proved
by means of electromigration (Table 3)- In Table 4 the instability con-
stants of the phosphate complexes of Pu(!V) were compared with those of
tlio complaxon with other acid-anions, and the following order was 'foundt
CO 2- _~' Hp02- 02- There are 3 figures, 4 tables, and 5 referencess
3 4 > C2 4
4 Soviet and 1 American.
SUW1ITTED3 March 10, 1959
Card 3/3

SHEVCHENK.07j.~~.; FFIDOROV, I.A.; AGUREYEV, Yu.P.
(Temperature effect on the extraction of the nitrates of
uranyl, plutonium, and nitric acid with tributyl
phosphate] Vliianie temperatury na. ekstrak-tsiiu tributil-
fosfatom nitratov uranila, plutoniia i azotnoi kisloty.
Moskva, Glav. upr. po ispolIzavaniiu atomnoi energii,
1960. 19 p. (MIRA 17:1)
(UraiVI nitrate) (Plutonium nitrates)
(Butyl phosphates)

SHEYCHEEKO, V.B.; SHMIDT, V-S-; MCNAROKOMOV, E.A.; PETROV, K.A,
Extraction of nitric acid vith tri-n-oct7lamine. Zhur. neorg
khim- 5 no.8:1852-1856 Ag ,6o. (KIRA 13:93
(Nitric acid) (Oatylamine)

ISHEVCBENKO, V.B.; SHKIDT, V.S.; MEZHOV, E-A-
Extraction of plutonium vith tri-n-octylamine from bydrochloric
acid solutions. Zhur. neorg. khim- 5 no-8:1911-1913 Ag 16o.
(MIR& 13:9)
(Plutonium) (Octylamine)

SHEVCHMTM#- Y.B.; RRIARD, Z.V.; SOWVKIN, A.S.
Extraction of trihydorzyglutaric acid into tri-n-butyl phosphate.
Zhur. neorg. khim. 5 no.10:2350-2353 0 160. (MIU 13:10Y
(Glutaric acid) (Baty-1 phosphate)

8ha
9
S/0 8 601005101010191021
YB C'
4
j 0 B004 B067
AUTHORS: Shevchenko, V. B., Shmidt, V. S., Nenarokomov, E. A.
TITLE: Extraction of Uranium(VI) by Means of Tri-n-octylamine
From Nitric Solutions
PERIODICAL: Zhurnal neorganicheskoy khimii, 1960, Vol. 5, No. 10,
pp. 2354-2362
TEXT: The authors wanl'led to make a detailed study of the extraction of
U(VI) by means of solutions of tri-n-octylamine (TOA) in o-xylene and
carbon tetrachloride. In an earlier paper (Ref. 10), it had been found
that in the presence of free nitric acid the entire TOA is contained in
the organic phase as TOA-HNO3. Therefore, the authors write down the
following equation for the extraction of uranium:
TOA.HNO + U02+ + 2NO- Ir- (TOA.H)U`0 (NO (1). The
3 org 2 aqu 3 aqu 2 3 3 org
dependence of the distribution coefficients on the concentration of free
TOA.HNO3 in the organic phase was studied at concentrations of 4.3 and
Card 1/4

84U9
Extraction of Uranium(VI) by Means of S/078/60/005/010/019/021
Tri-n-octylamine From Nitric Solutions B004/BO67
5.4 mole/l HN03 in the aqueous phase. In this connection the fact that,
according to Ref. 10, the concentration of TOA.HN07, varies in the organic
phase as a result of the reaction
H+ + NO3 aqu + TOA.HNO ITOA. HN031 (5), was taken into
aqu 3 Org 'HN03
account. By using o-.xylene as solvent the constant, K3 of this reaction
was found to be 0.13. Table 1 gives the values for the distribution
coefficient a~ Fig. 1 shows that with K3 = 0-13 the distribution
coefficient a increases linearly with the concentration of TOA.HN03. At
4.3 mole/l HNO 3 aqu and 0.470 mole/l TOA.HNO 39 a is 1.81, at 5.4 mole/l
HN03 it is 2.50. Fig. 2 shows a as a function of acidity of the aqueous
phase. a passes a maximum at 6 - 7 mole/l HN03. The decrease of a with
higher acid concentrations is explained by the formation of
(TOA.HN03).HN03 and by the occurrence Of U02(NO3)3 ions. In Fig, 3 a is
represented as a function of [H+], in Fig. 4 as a function of the uranium
concentration. o-xylene and carbon tetrachloride served as solvents. With
very low uranium concentration in the aqueous phase a is almost independent
Card 2/4

84219
Extraction of Uranium(VI) by Means of S/078/60/005/010/019/021
Tri-n-octylamine From Nitric Solutions B004/BO67
of the concentration. It is concluded therefrom that no polymerization
occurs. With high uranium concentrations a decreases. This is explained
by the reduction of concentration of free TOA.HNO as a result of the
extraction process. In Fig. 5 the equilibrium dMribution of uranium
between aqueous and organic phase is shown at 0.47 mole/1 TOA.HN03,
dissol.ved in O-C6H4(CH3)2 or CC14. Table 2 gives the dependence of a on
the concentration of uranium in the aqueous phase and the values for the
stability constant K, of the comp1exA(TOA.H)UO2(NO3)3. These values were
sufficiently constant only at uranium concentrations in the organic phase
up to 0.10 mole/l. They amounted to 2.02t0.12 for 0.47 mole/1 TOA.HNO .3
in CC14 and 2.8810.!l in o-C 6H4(CH 3)2' The absorption spectrum xecordbd
by a 0 -2M (SF-2M) rec'ording spectrophotometer of the organic uraniuml 6/~
solutions in TOA is shown in Fig.'6. It considerably differs from the
spectrum of uranyl nitrate, it is similar.~ however, to the abs,orption
spectra of the trinitrate uranyl compounds. The optical density of
UO2(NO3)2 solutione in methylisobutylketone was measured at different
Card 3/4

84219
Extraction of Uranium(VI) by Means of S/07BJ60/005/010/019/021
Tri-n-octylamine From Nitric Solutions B004/BO67
concentrations of TOA.HNO3 (Fig. 7). The optical density attained a
maximum at a ratio UO 2(NO3)2 : TOA..HNO 3 ~1 : .1 which was also confirmed
by the composition (TOA.H)UO 2(NO 3) 3* The authors mention a paper by
V. M. Vdovenko., A. A. Lipovskiy, and M. G. Kuzina (Ref. 11). They thank
L. V. Lipis for having carried out the spectrophotometric, studies. There
are 7 figures, 2 J;ables, and 19 references: 6 Soviet, 6 US, 1 British,
2 French, and 1 German.
SUBMITTED: July 6, 1959
Card 4/4

85627
S/078/60/005/012/014/016
BO17/BO64
IZI,31 0 0
J .
AUTHORS: Shevchenko, V. B.,
------------------------
Shilin, I. V., Zhdanov, Yu. F.
TITLE: Behavior of Hexavalent and
tion of Uranyl Nitrate and
Phosphate Solutions _~l
Trivalent Chromiumplin the Extrac-
Plutonium Nitrate With Tributyl
V1
PERIODICAL: Zhurnal neorganichaskoy khimii, 1960, Vol. 5, No. 12,
pp. 2832-2840
TEXT; Published data (Refs. 2-4), show that in the uranyl nitrate ex-
traction with some organic solvents considerable amounts of chromium are
coextracted. The behavior of hexavalent and trivalent chromium in the ex_
traction of uranyl nitrate and plutonium nitrate with tributyl phosphate
solutions was studied. The dependence of the distribution coefficient
of hexavalent chromium on the tributyl phosphate concentrations was in-
vestigated. Hexavalent chromium was found to be ettracted with tributyl
phosphate, and the distribution coefficient of Cr + was found to increase
when the tributyl phosphate concentration is increased. The effect of con-
centration of hexavalent chromium upon the distribution coefficient of
Card 1/3

85627
Behavior of Hexavalent and Trivalent Chromium S/078/60/005/012/014/016
in the Extraction of Uranyl Nitrate and B017/BO64
Plutonium Nitrate With Tributyl Phosphate
Solutions
6+
Cr , and the effect of hydrogen ion concentration upon the distribution
coefficient were also studied. Data of Table 3 show that the distribution
coefficient rises with increasing concentration of hydrogen ions in the
aqueous phase. This proves the fact that the extraction of hexavalent
chromium occurs in the form of chromic acid. The following extraction
equation is given: H CrO + 3 TBP ---,,,H cro *3 TBP. Fig. 4 shows the d18-
2 4 2 4
tribution coefficient of hexavalent chromium as a function of the equi-
librium concentration of nitric acid in the aqueous phase. Prom the coursed
of the curve it may be seen that with increased nitric acid concentration
the number of associated chromic acid molecules is also increased. The ef-
fect of uranyl nitrate upon the distribution coefficient of hexavalent
chromium was investigated. At a concentration of ranyl nitrate higher
than 1 mole/l, the distribution coefficient of Cr9+ decreases. The effect
of the sodium nitrate concentration upon the Cr6F distribution coefficient
was also studied. The dissociation constants K 3 and K4 of the chromic
acid - tributyl phosphate ere determinedg and the following values
Card 2/3

85627
Behavior of Rexavalent and Trivalent Chromium S/07a/6o/005/012/014/016
in the Extraction of Uranyl Nitrate aiii B017/BO64
Plutonium Nitrate With Tributyl Phosphate
Solutions
found:-. [H+Iwater . 1HCrO 41water
K3 ~ [H 2CrO4 1.26
CrO .3 T~water
K4 ~ rH2 CrO4 org T3 - 0.535
142 4)watero org
Table 6 gives the experimental results of the extraction of trivalent
chromium. The extraction yield of trivalent chromium with tributyl phos -
phate is low, The solubility of chromium nitrate in tributyl phosphate is
shown in Table 7. The solubility of chromium nitrate in tributyl phosphate
rises with increasing tributyl phosphate concentration. There are 5 figures,
7 tables, and 10 references: 4 Soviet, 5 US, and I British.
SUBMITTED: August 11, 1959
Card 3/3

PHASE I BOOK MFLOITATION SOV/5613
Shevchenko, Viktor Borisovich., and Boris Nikolayevich Budarikov
Tekhnologiya. urana (Uranium Technology) Moscowj, Gobatomizdat., 1961. 329 p.
Errata slip inserted. 6.,000 copies printed.
Ed.: M. A. Borisovskaya; Tech. Ed.: Ye. I. Mazell
PURPOSE! This book is intended for students and aspirants at schools of higher
education specializing in the technology of the natural radioactive elements,.
and can also be used by engineering, technical, and scientific workers in this
and related fields.
COVERAM: The book discusses technological processes in the production, dressing,
and refinement of uranium ore to obtain metallic uranium and compounds of
uranium used as nuclear fuel. Processing steps from the reduction of uranium
ores to the refining and metallurgical stages are explained in turn. The
remaining chapters deal with the chemical and physicochemical properties of
the most important compounds of uranium and include a brief description of
the.geochemical characteristics of uranium ore. The author has based his
Card 1/7

Uranium Technology
SOV/5613
work on a lecture serlj~s entftled "Technology of the Natural Radioactive
Elements" vhich he gave at the Moskovskiy ordena. Lenina khi-iko-tekhnologi-
cheskiy institut im. D. 1. Mendeleyeva (Moscow "Order of Lenin" Institute
of Chemical Technology imeni D. 1. Mendeleyev) from 1958 to ig6o. No
personalities are mentioned. There are 92 references: 20 Soviet, 70 English,
1 Italian.. and 1 German.
TAME OF COM90TS:
Ch. I. Introduction 5
1. Brief historical outline 5
2. Importance of uranium in nuclear power engineering 3-1
3. Compounds of uranium used as nuclear fuel 12
4. Nuclear purity of uranium 13
5. Synopsis of the characteriatics of uranium ore 15
6. Basic steps in the technology of uranium production 16
Ch. II. Chemical and Physicocheioical Properties of Metallic
Uranium and of its Most Important Compounds 20
1. Place of uranium in D. I. Mendeleyev's periodic system
of elements 20
Card 2/7

SHEVCFM~(~v Y.B.; ZHDUIOV, Yu.F.
Factraction of sulfuric acid and uranyl sulfate with tributyl
phosphate. Radiokhimiia 3 no.1:7-9 161. (MM 14:3)
(Sulfuric acid) (Uranyl phosphate) (Butyl phosphate)

S/186/61/003/002/001/018
c;,9.- Z 0 B037/E4ig
AUTHORSs .�hje~henko V B. and Shmidt, V.S.
TITLEt Extraction of ruthenium and other fission products with
tri-n-octylamine ,(TOA) from nitric acid solutions
PERIODICAL: Radiokhimiya, 1961, Vol.3, No.2, pp.121-128
TEXTs The distribution coefficients of the most important
radioactive flasion products jiave been studied for extraction with
TOA from nitric acid solutions-. Results (determined as the ratio
of 0- or y-activities of equal volumes of organic and aqueous
phases) of experiments using,cal37, SOO, Cel4_4, Zr95 + Nb95, and
Rul06 tracers are shown in Table 1, from which it can be seen that
only Ru is readily extracted. The fact that elements *ith, io4z
which have the greatest tendency to form nitrate compl!~~e!t,_!,re boat
extracted with TOA Is Illustrated by Table ~'and is explained
-HN03
by-the TOA.HNO3 being bound to the central atom of the
extractable compound through the N03 group of the TOA.HNO3.
Ruthenium has a great tendency to associate with nitrate ions and'
consideration of the properties of the various ruthen-lum.nitrosyl
complexes explains the fact that ruthenium is appreciably extracted
Card 1/9

--2 2991-- -
S/186/61/003/002/001/018
Extraction of ruthenium ... E037/E419
with TOA.HNO from RuNo3+ solutions (Table 1). Slow hydrolysis in
aqueous nitric acid solutions yields a mixture of ruthenium
nitrosonitrates, the equilibrium proportions of the individual
compounds being determined by the HN03 concentration (Ref.21:
OoYe.Zvyagintsev, V.D.Nikollskiy, S.M.Starostin, A.Kurbanov,
V.S.Shmidt, Khimiya radioelementov i radiatsionnykh prevrashcheniy,
336. m. (1959). Ref.22: G.Rudstam, Acta Chem. Scand., 13, 1481
(1959). Ref.23: V.D.Nikollskiy, V.S.Shmidt, ZhNKh, 2, 2746 (1957)-
Ref.24: V.D.Nikollskiy, V.S.Shmidt, ZhNKh, 3, 2476 (1958).
Ref.25: V.S.Shmidt, Thesis, IONKh M. (1958). Ref.26: A.Jenkins,
A. Waint J.Inorg.Nucl.Chem., 3, 24 (1956) ). Preliminary
TOA.HN03 extraction studies showed that 6 hours were sufficient to
establish complete equilibrium. Ruthenium distribution
coefficients E measured'for complete equilibrium in the solution
of nitrosonitrates do not reflect the extraction behaviour of the-
most readily extractable forms of Ru (Fig.1). This figure alAo
illustrates the extraction behaviour for non-equilibrium conditions
in the aqueous phasel it can be seen that the d1stribution
coefficients are highest fbr low acidities and doe a* rapidly with
S"
incr:)asing HN03 concentration in the aqueous phase.--
Card 2/9

S/186/61/003/002/001/'018
Extract-ion of ruthenium E037/E419
.2,'on-equilibrium conditions if ere studied',using freshly-prepared.-
nitrosotrinitrate solutions for short contact times. Fig.2
illustrates 14u. distribution coafficients.for re-6xtrae'tion
(ba ck- extraction).. T."Ie"distribution doefficientsvary with the'
duration of the re-extraction and it seams that the'ruthenium
distribution-coefficients for TOXi= as for extraction with
31
tributyl-phosphate,are proportlonal to the d�strlbutlon
coefficients.of the most readily extractable compounds-. F ig .5 A
shows that the distribu~ion.coefficients of the most re'adily
extractable Ru nitroso-co 'mpounds are 15roportional to the square of
,thb TOA..,HN03 concentration in the organic Phase~ If it is
assumed that, as iri the case of tributylT)hosphate.ex'%.raction, thd
most readily extractable compound is Ru"O(D103)3 then it f olloirsi
from the data obtained that this pomppuAd goes into the organic.
Phase as the complex Ru1iO(NO3)3(TOA-"NO3)2- There are 3-fixure's,
2 tMbles and 27 references: 18 Soviet-bloc and 9 non-Soviet-bloc,
The four most recent referencos .~,o..Engllsh..language publications.
-3 hi
uc I.. en.
69 (1959); H.A.C.IMIcK6Y, J. inorg.' Nucl. Chem-9 9'2 5 6, 19 5 a-
ard' V 9
C

Extraction of ruthenium ... E037/F,1119*
R.A.C.I-IcKey, J. Inorg. Nucl. Chem., 271 (1956);
H.A.-C.14PRey, J. Inorg.Z.7ucl, Chem., 9, 278 (1958).
SUM-IXT-LED: March 30, 1960
Card 4/9

22992
S/186/61/003/002/002/018
E142/E435 -
AUTHORS: Shevchenko, V.B., Shmidtl V.S. and-Nenarokomov., B*A#
VI IV
TITLE., The extraction of U and U with the di-isoamyl ether
of methyl phosphoric acid from HCl solutions
PERIODICAL. Rad-'okhimiya, 1961, Vol.3, No.2, pp.129-136
TEXT. During the last few years di-isoamyl ether of methyl
phosphoric acid (DEMPA) has been used as a satisfactory extracting
agent for uranium. The authors mention briefly their previously
published results on the effectiveness of the compound and on the
stability of the hexavalent uranium complex, extracted with DEMPA,
eLs compared to the stability of the complex extracted with
&ributyl phosphate (TBP). The present investigation deals with
W
the reaction mechanism of extracting UVI and UIV-with DEMPA from
HC1 solutions; the stability of the uranium compounds, extracted
from the HC1 solutlons with the two aforementioned reagents is
compared. Of each reagent 20%solutions, in carbon tetrachloride,
were used. Details of the preparation of uranyl chloride (U02CI2)
and of uranium tetrachloride (UC14) are given. -Equal volumes of
the 2 phases (10 ml each) were used for the extraction process
Wh'-sh lasted 10 minutes& this time sufficed for attaining
Card 1/2

22992
S/186/61/003/002/002/Oi8
The extraction of UVI and UIV E142/E435
equilibrium, The solution was allowed to settle for 18 hours
(UVI) and 1 hour (UIV) respectively; thereafter the phases were
separated. Each phase was analysed for its uranium content and
the dispersion coefficient defined as the ratio of the
concentrations of the element in the organic and in thp aqueous
phase. During the extraction of hexavalent uranium it was found
that UVI is extracted to an appreciable degree with a. 20% solution;'
of DEMPA in CC14 at acidities > 2N HCl. The tetravalent element
is extracted satisfactorily with 20% solutions of DEMPA and TBP in
CC14 only at concentrations of HC1 >4 -5 N HC1. The compl~ax '- -
U02CI2.2DEMPA was formed in the investigated acidity ra~;e (up td'
5N HC1); tetravalent uranium forms the complexes UC'4.12DEHPA and
UC14.2TBP. The ratios of the stability constants were calculated
for the complexes U02C12.2DEDEPA and U02Cl2.2TBP (113 � 16) and for
the complexes UC14.2DEMPA and UC14.2TBP (approximately 300).
There are 4 figures, 5 tables and 7 references: 5 Soviet-V~oc and
2 non-Soviet-bloo. The 2 references to English language %.-
publications read as follows: K.Kraus, P.Nelson, J.Am.Chem.Soc.,
72,3901 (1950)1 R.Betts, R.Leigh, Canad.J.Res., 28B,514 U953).
SUBMITTED: April 30, 1960
Card 2/2

22485
s/186/61/003/003/003/oi8
E071/E435
AUTHORS: Shevchenko, V.B., Fedorov, I.A. and Smelov, V.S.
TITLE: The Influence of Temperature on Extraction With Mixed"
Solvents of Uranyl Nitrate and Tetravalent Plutonium
PERIODICAL: Radiokhimiya, 1961, Vol-3, No-3, pp.256-260
TEXT: The influence of temperature on the extraction of uranyl
nitrate and tetravalent plutonium from 2M nitric acid solution with
a mixture of diisoamyl ester of phosphoric acid (DAPh) and
tertiary butyl ester of phosphoric acid (TBPh) in xylene was
investigated. In the case of extraction of uran nitrate, the
concentration of DAPh in the mixture was 1.9 x 19~31 and that of
TBPh was 6.3_x lo-3 m; and for extraction of Pulivr 1 2.1 x 10-4m
and 2.1 x 10 2 M respectively. The co centratioil of uranyl nitr te
in the starting solution was 3.15 x 10'tM, of Pu(IV), 1.05 X 10-4M-
The concentration of nitric acid In starting solutions was 2M.
The limits of concentrations of TBPh and DAPh in the organic solvent'N
and of nitric acid in water were chosen in order to obtain a
maximum synergetic effect. The--extraction experiments were done
in thermostatically controlled (+ 0.1*C) separating funnels with
Card 1/-k

22485
s/186/61/003/003/003/018
The Influence of Temperature ... E071/E435
10 ml starting volumes of phases and within the temperature range
of io to 6oOc. Uranium and plutonium were determined in both
phases by the radiometric method. The valency state of
plutonium was spectrophotometrically controlled. The coefficient
of distribution a was determined as the ratio of analysed
concentrations of the substance investigated in the organic and
aqueous phases. The synergetic effect of the mixture was defined
as a ratio of the coefficient of distribution on extraction with a
mixture to the sun, of coefficients of distribution of the
substance investigated on extraction with each individual solvent.
The temperature dependence of the distribution of uranyl nitrate
and tetravalent plutonium on extraction with the mixture of
DAPh and TBPh (curve 1), with DAPh (curve 2) and TBPh (curve 3)
is shown in Fig.1 (for uranyl nitrate) and Fig.2 (for tetravalent
plutonium). Using determined values of coefficients of
distribution on extraction with individual and mixed solvents, the
equilibrium constants for the reaction of formation of respective
mixed complexes were determined. On the basis of the-
experimental results obtained, it is concluded that the
extractability of uranyl nitrate and plutonium (IV) with a mixture
Card 2/'~4- ~

The Influence of Temperature E071/E435
of DAPh and TBPh in xylene'decrease with increasing temperature
from 10 to 600C. With increasing temperature from 10 to 600C, the
equilibrium constant for the formation of mixed cojpplex
U02 I(C5HllO)2POO12TBPh deervased"firom.2.20 X 104 to 0-87 x 104*
while the constant for the mixed complex PU[(C5HllO)2POO14TBPh
changes-only a little.. There are 2 figures, 2 tables and
8 references-: 5 Soviet-bloc and 3 non-Soviet-bloc. The three
references to English le~nguage publications read as follows:
H.Irving, D.Eddington, Proc.Chem.Soc., 11, 36o U959);
T.Sato, Gall.Bull.Inst.Nucl.Sci., 7, 43 (1957); Z.Disdar,
J.Inorg.Nucl.Chem., 6, 334 (1-958)..
SUBMITTED: May 31, 196o
Card

SHEVCHEDIKO, V. B.; SOLOVK11N, A. S.; KIRILLOV, L. M.; IVANTSOV, A. 1.
Effect of saturated monoatomic.alcohols and ethers on the
extraction of 1 t27- , Fu M , Zr M , Ca1w, ~Lnd Nby:with tri-
n-butyl phosphate from nitric acid solutions. Radiokhimia 3
no-4:35-6 161 ?Extraction(Chemistry)) (MIRA 14:7)
(solvents)

33184
S/186/61/003/oo6/003/010
I. 4zo o E040/E185
AUTHORSs Shevchenk and Zhdanov, YU.F.
TITLE.~ Behaviour of plutonium during its extraction with
amines from sulphate solutions. 1. Extraction of
sulphuric acid and tetravalent plutonium sulphate
with n-trioetylamine (TOA)
PERIODICAL., Radiokhimiya, v-3, no.6,, 1961, 676-684
TEXT.- 131 mixtures (by volume) of the test solution and
trioctylamine solvent (dissolved in carbon tetrachloride) were
shaken for 5 minutes, the phases formed were separated by
centrifuging and the concentrations of sulphuric acid in the
aqueous and organic phases were determined volumetrically using
phenolphthalein as indicator. Equilibrium concentration of
plutonium was determined radiometrically. An analysis of the
experimental data obtained for the extraction Of H2SO4 with
n-trioetylamine showed that, assuming practical insolubility of
TOA in the aqueous phase, TOA sulphate and bisulphate are formed
in the organic phase at sufficiently high concentrations of
Card 1/4

33184
Behaviour of plutonium during its ... S/186/61/003/006/003/010
Eo40/El85
sulphuric acid, Equations are derived for the concentration of
both sulphuric acid and TOA bisulphate in the organic phase.
The equilibrium constants of the two compounds are, respectively,
K = 1.18 and K = 0.279 x 10. The distribution coefficient of
sulphuric acid between the two phases was found to be independent
of the sulphate ion concentration, provided that the second
stage of sulphuric acid dissociation can be ignored. The
distribution coefficient of sulphuric acid was observed to
increase with rising TOA concentration. Data are also reported
for the effect of Li2SO4 on the extraction of sulphuric acid with
trioctylamine, It was assumed that the extraction process of
tetravalent plutonium sulphate with n-trioctylamine can be
expressed by the equationsi
(R3NR) 2SO4 + PU 4+ + 2SO 2- pj (R NH) PU
B 4B 3 2 (S04)30
+ PU4+
2R-NH9SG4 + 2SO 4 *---- 3~ ( R3NH)2Pu(SO 4)3+ H' + H2so 4
- -0 B B 0 B B
Card 2/ 4

33184
Behaviour.of plutonium during its .. s/186/61/003/006/003/010
E040/E185
or 2R N + H + + HS04 + PU 4+ + 2S0 2- 0 (R NH) PU (SOO
3 0 B B 4
B B 3 2 30
R N + R NH S04 + Pu 4+ + 2SO 2- j--J (R NH) PU(SO4) + H ++ HS04
3 0 3 2 0 B 4B 3 2 30 B B
The value of the extraction constant, deducted by graphic method,
is 1.15 x 105. The distribution of plutonium sulphate between the
aqueous and organic phases was found to depend on the relative
concentrations of the sulphate and bisulphate of TOA: the
distribution coefficient diminishes with an increase in the
relative concentration of TOA bisulphate. Data tabulated for
the effect of sulphuric acid concentration on the distribution
coefficient of plutonium sulphate show that the distribution
coefficient of plutonium sulphate rises at first with increasing
H2SO4 concentration and then drops. This is hought to be due to
an initial inhibition of the hydrolysis of PuV compounds at
sulphuric acid concentrations in aqueous media up to 0.1 M and,
at higher H2SO4 concentrations in the aqueous phase, the
Card 3/4 X

. . - 33184
Behaviour of plutonium during its ... S/186/61/003/oo6/oO3/010
Eo40/El85
concentration of the amine bisulphate in the organic phase tends
to rise and lowers the extraction efficiency. Curves plotted for
the influence of lithium sulphate on the distribution of
tetravalent plutonium between the sulphuric acid and trioctylamine
phases show initially a sharp rise and then a pfogressive
reduction of the distribution coefficient of Pu +.
There are 4 figures, 4 tables and 22 references: 3 Soviet-bloc,
2 Russian translations of non-Soviet-bloc publications~ and 17
non-Soviet-bloc. The four most recent English language
references read as followss
Ref.10., C.F. Coleman, K.B. Brown, J.G. Z*foore, K.A. Allen. Paper
at the Second Geneva Conference no.15 (P), 510, 1959.
Ref~15i D.J. Carswell, J.J. Lawrance,
J. Inorg. Nucl. Chem., v.11, 1, 69 (1959).
Ref.161 J.L. Drumond, J.Chem.Soc., 3218 (1958).
Ref.20i D.J. Brown, J. Colloid Sc., v.13, 3, 286 (1958).
SUBMITTEDg November 21, 196o
Card 4/4

B1 21 YB'
208
AUTHORS% Shevchenko, V. B., Smelov, V. S.
TITLE- Extraction of nitrates of cerium, europium, and yttrium by
dibutyl phosphate
PERIODICALi Zhurnal neorganicheskoy khimii, v. 6, no. 3j 1961, 732-737
TEXT: Extraction of cerium, europium, and yttrium by dibutyl phosphate
was studied for the purpose of separating cerium and.europium from yttrium.
Thiophene-free benzene was used as solvent for dibutyl phosphate. Equal
volumes of the rare earth - nitrate solution and the organic phase were
allowed to stand at 200C for 15 min until equilibrium was attained. The
0
separations were observed by means of the radioactive tracers Ce144' Y9
and Eu152 and Eu154. The distribution coefficients of trivalent cerium,
europium ', and yttrium were studied as a function of their concentrations;
the distribution coefficients of ceriu3n and yttrium were found to be
practically independent of the concentrations. This fact confirms that
cerium and yttrium do not form polymers at Q.1-2 moles/I HNO The de-
Y
Card 1/3
S/07 01/006/003/017/022

S/078/61/006/003/017/022
Extraction of nitrates of... B121/B208
pendence of the distribution coefficients of trivalent cerium, yttrium
and europium on the dibutyl-phosphate concentration was studied at ENO 3
concentrations of 0.1 and 0-5 mole/l. It was found that the distribution
coefficient decreases with reduced dibutyl phosphate concentration in the
organic phase, but, increases with decreasing HNO 3 concentration. A HNO3
concentration of 0.1 mole/1 in the aqueous phase, and a dibutyl phosphate
concentration of 0.1 mole/l in the organic phase are recommended as the
optimum for the separation of cerium and duropium. from yttrium. Under
theme conditions, the distribution'coefficients of the systems yttrium. -
cerium and yttrium - europium are 4.10 2 and 5-5.102, respectively. The
authors mention the possibility of separating rare elements into the cerium
and yttrium groups by extraction with dibutyl phosphate. The equilibrium
constants of the reactions of cerium-pd yttrium with dibutyl phosphate
were balculated to be (3-5 � 0-0-10 for cerium and (1.33 t 0-1)-102 for
yttrium., V.V. Fomin and Ye. P. Mayorova are mentioned. There are 3 figures,
Card 2/3

S/078/61/006/003/017/022
Extraction of nitrates of ... B121/B208
2 tables, and 40 references! 13 Soviet-bloc.
SUBMITTED: August 11, 1959
Card 3/3

23086
S/078/61/006/006/012/013
B110/tN6
AUTHORS: Denotkina, R. G., Shevchenko, V. B.
TITLE: The separation of phosphate complexes from plutonium (IV)
solutions
PERIODICAL: Zhurnal neorganicheskoy khimii, v. 6, no. 6, 1961, 1476-1478
TEXT: As is known, uranium (IV) and thorium form complex compounds with
the ions of phosphoric acid. Since with regard to its chemical properties
tetravalent plutonium is very similar to U (IV) and Th, it must form
complex compounds with the phosphoric acid ions. This is confirmed by the
solubility of Fu compounds in H 3P0 4* The experiments conducted by the
authors on the separation of Fu(IV)-phosphate compounds confirm their
existence in the solution. A compound with good solubility in the
presence of phosphate ions had to be selected for establishing the
complex formation of Pu (IV). Hydroxide and doubly substituted Pu
(IV)-phosphate were selected as initial substances. Pu(HPO 4)2-xH 20 is
well soluble in 3.9 and 2.8 molar H 3P04 solutions. With the reduction of
Card 1/6

23086
S/07a/6i/oo6/006/012/013
The separation of phosphate complexes ... B11O/B2o6
the phosphate ion concentration, the solubility of both compounds drops,
however, and no complex compounds can be separated from the solutions
because of the low Pu concentration. Freshly precipitated plutonium (IV)
hydroxide, from which Ne- and NO--ions were washed out, was dissolved
4 3
at room temperature in 6 mole H 3PO 4* The doubly substituted Pu (IV)-
phosphate was obtained by precipitation by 0-4 molar H 3PO4 from 1-molar
plutonium solution combined with nitric acid. The precipitate washed out
with 0.6 mole HNO 39 C2H 5OH and ether was dissolved in 6, 3.9 and 2.8 molar
H3 PO4. Pink solutions form when dissolving hydroxides and Pu(RPO 4)2. XH20
in H3PO 4' The composition of the Pu(IV)-phosphate complexes in these
solutions was determined by the solubility method. The precipitation of
the compounds mentioned made it possible to check the composition and to
investigate the properties. Ethyl alcohol was used for salting out the
phosphate complexes. Gelatinous, faintly pink-colored precipitates were
deposited when phosphate solutions of Pu(IV) were added to the alcohol.
The precipitates freed from the mother liquor and washed out in alcohol
Card 2/6

23o86
S/078/61 oo6/006/012/013
The separation Of Phosphate complexes ... B110/B20~
and ether were dried in the air thermostat for 24 hr at 25 1 50C and in
vacuum for 6 hr. The constant composition of the products prepared was
achieved under the given conditions. The analysis results of the sub-
stance separated from 6 mole H 3P04 are shown in Table 1. It can be seen
therefrom that during the dissolution of the hydroxide and the doubly
substituted phosphate in 6 mole H 3PO 4, a complex compound with the ratio
Me : addendum = 1 : 5 is separated, which probably corresponds to the
formula H6 [Pu(HPO 4)51 -nH20. The analysis of the compounds separated
from 2.8 - 3.9 H 3PO4produced a ratio of 1 : 5 (Table 2). The Pu(IV)
complex compound with four phosphate groups was separated from the mother
liquor, which was obtained during the precipitation of Pu(IV) with 1.2
and 1.6 mole H 3 PO4 from its 2-molar nitric acid solution. According to
Table 3, the ratio Pu4+ - 2- 0
. HPO 4= 1 : 4. This composition corresponds t
H4 lpu(HP04)41 - nH20. Studi6s of the electromigration of Fu(IV) confirm
the existence of complex acids. Pu(IV) complex compounds with five
Card 3/6

23086
The separation of phosphate complexes ... S/078/61/006/006/012/013
B110/B206
phosphate groups probably exist in 6, 3.9 and 2.8 molar H PO ) and those
3 4
with four groups in 1.2 and 1.6 molar H3PO 4- The complex with the ratio
Me : addendum = 1 : 3 could not be separated. The solid phosphate
co mplexes are amorphous pink substances, well soluble in ENO 3 and HCI,
insoluble in alcohol, hexane, ether, acetone and carbon tetrachloride.
After six months storage they still had the original ratio pu4+ : Hpo 2-
4
and were hydrolized in water (Abstracter's note: Essentially complete
translation-' There are 4 ta~les*and 5 references: I Soviet-bloc ahd 4
non-Soviet-bloc. The references to the English-language publications
read as follows: Ref. 1: E. L. Lebroski, H. W. Ater, F. K. Neuman,
J. Amer.*~Chem. Soc., 73, 5646 (1951). Ref. 2: J. M. Schreyer. J. Amer.
Chem. Soc. 77, 2972 (1955). Ref. 3: R. P. O'Connor. Report CN, 1702, June,
1944.
SUBMITTED: November 3, 1960
Card 4/6

SHUMMKOP V.B.,- SH-.LOV, V.S.
Effect ol temperature on the distribution of mono- and dibutYl
phosphoric acids between benzene and water. Ekstre; teor'*-j'Primq,,-
app. no.2:58-.62 162. (MA 15:9)
(Phosphoric acid) (Solvents)

SHEMEMEOY V.B.; SMELOV, V.S.; STRAKHOVA, A.V.
Synergism in the extraction of uranyl nitrate. Ekstr.; teor.,
prim.,,app. no.2:179.;,-189 162. (MIM 15:9)
(Uranyl r4trate) (Fxtraction (Cheridstry))

I SHEMMIKO, V.B.; SMELOV, V.S.
Effect on mono- dibutyl phosphates on the extraction of uranium 011)
by tribrutyl phosphate. Ekstr.; teor.,Drim.,app. no.2:219-226 162.
A ~
- (MIRA 15:9)
(Uranium) (Butyl phosphate)

V,,B.; SIUILOV. V.S.
Problem of th~ extractinn of fission products by monc- and '.
dibutyl phosphates. Ek3tr.; teor.,primo,appq no.2:257-263 '62. -
WIRA 15:9)
(Fission products) (Butyl phosphate)
(Extraction (Chemistry))

S/078/62bM7/007/012/Oi3
B119/h101
AUTHORSi Shevchenko, V. B., Smelov, V. S., Strakhova, A. V.
TITIM,& Extraction of uranium by a binary reagent mixture
PERIODICALt Zhurnal neorganichaskoy khimii, v- 7, no, 7, 1962t 1736 -1742
TEM The authors studied extraction of uranyl nitrate from aqueous solu-
tions by binary mixtures of diisoamyl ester of phosphoric acid W, mono-
isoamyl ester of methyl phosphinio acid (Ii)(acid components), tributyl
phosphate (III), diis6amyl ester of methyl phoaphinic acid (IV), and tri-,
bubyl phosp4lnic oxide (11)(neutral components). The diluents used for the
orCanic phase were carbon tetrachloride,.chloroform, tridecane, octane,
berizeno, xylene, tri-1, 2, 3-propyl benzene$ as well as the high-boiling
fraction of hydrogenated kerosene (both in its crude state and rehydro-
genated and redistilled). u233 was used in concentrations of - 1o-4
Moles/liter. The method of investigation was as described by the authors
earlier.(Sb. po ekstraktaii, (Collection on Extraction) Atomizdat,. lq62)..
Resultsi for the extraction with II + III the maximum values of the
synergetic extraction,effect S were shown to occur with 8 to 10 times as
mi.tch of 11 orpsent in benzene solution as required to form
Card - 1/3
vr,

JD'
A
--~-~-~xt-A-P%272-ol~- SOURCE CODE:: -UR/007,W63~/010/01112
AUTHOR: Denotkina, G' Moskvinj -A. I.,
R. .'Shevehenko, V. B,
ORG: None
TITLE: The solubility product of ammonium osphate in
plutonil'.
aqueous solutions
SOURCE: Mirnal neorg cheskoy 1(hirnif" v. lot no., ill -;A52
ani
1965.,-244q
TOPIC TAGS: ni osphates plutoniuii compo-4nds solubility
ph
ABSTRACT: Ammonium plutonyl phosphate was precipitat 3A bj the'.5daction
of a 6.1 molar nitric acid plutonyl solution with an'e,26 x 10 molar.
concentration of the metal and a 1.0 molar solution Of (KHOPHP0110 The
finely crystalline preeipitate.obtained., whichwas of a 1-I& grden
color and had the composition Nff4FUO PO 03H 0. was the'starting material
for the investigations, IW., sollibilitr;40-f j;mo;~uzm pluton-11- to
PMSPna
was determined in aqueous solutions over the 1~ff range from 1.0 to 6.k:.
In one series of experiments the pff of the solaticas was adjusted by
addition of HC1041 and In another series of experimuts by additim of
HITO-As 'Las ionic strength in the solution was not constantj, since.
addItion of NaC310h or LiNO3 to maintain mu constant brougWabout
partial replacemefit of the WJ~4 group or lithium-ionsp as a
Card 1/2 M)C: 546-799-41391185
e-A

AYRUNI, Arsen Tigranovich, kand. tekhn. nauk; ALER3ETEV, Viktor Borisoviph;
BURSHTEYN, Mark Aleksandmvislh; Cx-EYW, Leonid Mikhaylovich;
GRABILIN, Yuriy Nikolayevich; KILD4DV, Sergey Leonidovich; SOSNOV,
Vladimir Dmitriyevich; SPENCII&VA, Valentina Ivanovna; SUMIN,
Georgiy Georgiyevich; FEYGIN, Lev Mikhaylovich; SHEVCHENKOP -Vadim
Dmitriyuyiah; KAZAKOV, B.Ye., otv. red. toma; TAYTS, T.L., red.;
OSVALID, E.Ya., red. iad-va; MMK&R, L.I., tekhn. red.
[The coal industry of capi'talist countries]Ugollnaia promyshlen-
nost' kapitalistichaskikh stran. Moskva, Gos.nauchno-tekhn.izd-
vo, Iit-ry po gornomu. delu. Vol.2.[T-echnology, mechanization, and
organization of development workings]Tekhnologiia, mekhanizataiia.
i organizatsii rabot pri provedenii podgotovitellnykh gornykh Ty-
rabotok. Otv. red. toma: B.E.Kazakov, V.D.Sosnov., G.G.Suetin.
1962. 351 p. OKM 16: 2)
1. Moscow. TSentralinyy institut tekhnicheskoy informatsi-i ugollnoi
promyshlennosti. 2. TSentrallnyy institut tekhnicheskoy informa-
tsii ugollnoy promyshlennosti, Mbsaost~for suvetin, sencheva).
3. Gosutl- stvenn ro dktnyy institut po, avtomatizatsii ugollnoy
i ly P y
promyshlennost 'for Feygin). 4. Gosudarstvennyy komitet Soveta
Ministrov SSSR po avtomatizataii i mashinostrayeniyu (for Sosnov).
5. Vsesoyuznyy tsentraltnyy proyektnyy institut po proyektirova-
niyu shakhtnogo stroitel'stva. kamennougollnoy promyshlennosti (for
Burshteyn, Shevahenko). 6. Gosudarstvennoye nauchno-tekhnicheskoye
izdatel'stvo po ugollnoy promyshlennosti(for Geyman).
(Gentinaed-en-nextb,~~

'~.D..;-,SHKLYAR, L.A., kand. tekhn. nauk, red.;
VAGAFOV, E.A., red.
[Learn how to drive a car] Uchites' upravliat' avtomo-
bilem. Kazan' Tatarskoe knizhnoe izd--%,o 1965. 194 p.
WRA 18:10)

SHEVCHENKO, V.D., inzh.; PERMYAKOV, Yu.V., inzh.
. - - --'--~~sd-ni--ihe SKG-30 track-laying crane with 55M. guying crane arm,
Prom. stroi. 41 no.10:49-50 0 163. (MIRA 16:11)

-SIIEVCIIEIIKO V D - SELITSKIY, F.I.
Use of epoxy resins for the correction of founding defects.
Lit. proizv. no.12:33 D 161. (MIRA 14:12)
(Founding-Defects)
(Epoxy resins)

SHEVOROKO, V.D. (YiyeY)
Equations for calculating shallow shells, Prykiomekh. 8 no.4:368-
371 162. (MIRA 15:9)
1. Kiyevskiy avtomobiltno-dorozhny.~ institut.
(Elastic plates and shells)

-7 1 ~F- 7 ---- ---
ACCES$W! MR IS1019816JI
A~~0055 43 .909/004/0)67/03
r
AUMO~~ t Sheichenko.' V. Do
1; ETLEI The effect.of 'certaip geometric paramo ~.ers,'on the'stress-deformed state
f I ~ I . . I
iA amllow s*hblls
URCE i - Pry*kladna mekhainika, v. 9,, n4- 41 1963j. '367,37f.
TOPIG 'VAGS C shall:ow shellp sag force., 'not e'i ~Aagep ooeffiaient-
f a' dif.ferenc
f
ABSTRACr i The author uses two methoila to. find'values for saes tnd
forces (which
are shown toi-depond on the cooffiaient'of bulg 6fthe shell)*1. 'the mothod of
finite diff6rences and the method of nets. 1% the.thicknesb oftba not is in--
creaso'dj t4e a6curaoy of the valuca for sags and forces hi6 * greater.. and it is
shownithat an accuracy greater than 5% is obtain'ed..using'd. 6 x 6 not.. Considers-
#ons,:Are presefited as to the .shaUawnesa of tile
Th6 in6thod of finite differences is used to fiAd. the Appendexi e of angsj forces'
and momenta. of hiiiged shells'on the coefficient" of. bulge Cor,.,tbr6e-. cases:
it 2 000' ~(Sse figures, 1., ,The iuthoe...drawi, a, son with moment-
95P /11 edmnhri
less th,eoxyo
t

-4T (d IF Iw? (w) IF WA (d)/FWP(v)/r=WP (k)/FWA(h) Pf-4/Peb EM
ACCESSION NR: AP5607268 S/0198/65/001/riOZ/0056/0061
AUTHORi Shevchenko, V. D. (Kiev)
TITLE: Nonlinear flexure problem of a shallow shell-
SOURCE: PrikladnayR mekhanika, v. 1, no. 2, 1965, 56-61
TOPIC TAGS: shallow shell, shell flexure, shallow shell flexure
ABSTRACT: The solution of the problem of flexure of a shallow shell
in nonkinear formulation by the method of finite differences combined
with an iteration method is presented. V. Z. Vlasov's system of non-
linear differential equations is reduced (by means of finite-differ-
ence relationships) to a system of nonlinear algebraic equations to
which the linear theory of shallow shells can be applied. The proce-
dure of solution by using an iteration method is outlined. The range
of application of the linear theory, is discussed by comparing the re-
sults obtained by applying nonlinear and 'linear theories to shells with
various depth and rigidity parameters. The problem is solved on an
electronic computer for simply supported and hinged shells having the
jCard 1/2

L 34094-65
ACCESSION NR: AP5007268
form of an elliptic paraboloid, and the deflections In the center of
the shell are determined and shown in diagrams. Orig. art. has: 2
figures, 1 table, and 14 formulas. (VKI
ASSOCIATION: Kiyevskiy avtodorozhnyy institut (Kiev Highway Institute)
SUBMITTEDi 03Apr64 ENCLOSUREi 00 SUB CODE: AS
30 REF SOV: 003 OTHER: 000 ATD PRESS: 3209
:Card 2/2

SHEVCMNKOJ, V.D. (Kiyev)
Nonlinear problem of the bending of a shallow shell. Prikl.
mekh. 1 no.2:56-61 165. 04IRA 18:6)
1. Kiyevskiy avtodorozhnTj institut.

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nre s in the Chrr~ict-~riotlcs~ of thf,- Enq;lue DariLtlj; Acceli-truticn, 5b. statty
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VOSKRESENSKIT, B.V.; MIRONOV, N.P.; SHEVCHENKO, V.P., mekhanik
Production of high-qualit7 engineering lime. Stroi. mat. 5 no.4:22-24
Ap '59. (MIRA 12:6)
l.Glavny7 inzhener Chelyabinskoge zavoda ferresplavov (for Voskresenskiy)o
2.Nachalinik tsekha Chelyabinakogo zaveda ferrosplavav (for Mironav).
(Chelyabinsk--Idme)

SHEVCHEWO V.I.
-
Nachine tool for punchiug_A4pip~.stesl. [Suggested by: V.I. Shavchanko].
Rats. i izabr. predl. v strei. no.142.-14-16 156. (MIRA low-4)
(Punching machinery)

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Uping.sheit.steel waste Instead of angle steel in making fitting
frames. [Suggested by: T.F. Sheychinkaj. Rate. I isebr. predl. v
stroi. no.142:39-41 156. (MLRA 10:4)
(Ventilation)

SHEVGHMM, V.1F.
Manufacturirg frameleas air-regulating vents to be used for air
curtaina. Rats. i izobr. predl. v stroi. no,3:83-85 157.(XUU*lltl)
(Air curtains)

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Manufacturirg strainers to
predl. v stroi, U093:85-88
be used in oil filters. Hats. i izabre
157. (MIRA. lltl)
(Oil filters)

SERnmemo. V.F.
ur ng frameless air vents to be used in the T.T. Baturin
s.,rstem. Rate. i izobr. predl. v stroi. no.3:88-90 157. (MIRA 11:1)
(Factories-Heating and ventilation)

SENYCBMW, V.FI
Ifanufacturing frameless air vents to be used in crane cabs. Rats.
i izobr. predl. v stroi. no.3:90-91 157. (MIRA 11:1)
(cranes, derricks, ate.) (Ventilation)