Radiolytic Yield of UIV Oxidation into UVI
saturated solutions. In fact, under N
O, the radical HO ·
J. Phys. Chem. A, Vol. 114, No. 5, 2010 2081
2
2
is not
formed. Under this condition, we compare the yield of radiolytic
To analyze the gases produced during irradiation, another
IV
series of samples were studied. The U solutions were irradiated
IV
VI
U
oxidation with the yields of radiolytic formation of U and
in another specific polypropylene cell equipped with a valve,
after being filled with nitrous oxide at a pressure equal to 1.5
( 0.15 bar. After each irradiation, the molecular hydrogen and
other gases were measured using an original connection device
between the irradiated sample cell and the mass spectrometer
gases. On the basis of the quantitative results obtained on these
yields, we revisit the mechanism of the oxidation process and
V
discuss also the occurrence of the U disproportionation reaction.
Experimental Section
(
Minilab Residual Gas Analyzer from MKS). Before calibration
The solutions were prepared using ultrapure water from a
Millipore system (18 MΩ cm) and reagent grade chemicals used
without further purification: HCl, 37%, from Normapur; NaCl,
and gas analysis, a cleaning of the setup is performed with pure
argon to remove any trace of atmospheric gases. The calibration
of the gas analysis involves two steps. During the first one, the
signals of the relative gas pressures are calibrated in atmospheric
air by using a Faraday detector and assuming 1% for the relative
pressure of argon. In the second step, high-purity argon is
injected to determine the different proportions of the isotopes:
ACS reagent, with g99.8% purity from Sigma-Aldrich; N
2
and
N
2
O with 99.99% purity from Air Liquide. To study the
IV
radiolytic oxidation of an aqueous solution of U , it is first
necessary to synthesize a pure solution of this oxidation state
of uranium. For that purpose, an aqueous solution of hexavalent
40
36
38
Ar, Ar, and Ar. Three electron-multipliers are used for
uranyl nitrate, UO
uranium metal oxidation with nitric acid, is reduced under N
by applying a constant electric intensity between two electrodes.
2
(NO
3
)
2
(H
2
O)
6
, which has been obtained by
measuring separately the three argon isotopes. For the sample
gas analysis, argon was used as the carrier gas with a flow rate
2
-
1
of about 5 mL min
. Two measurements were performed for
-3
-1
Solutions containing 100 mL of 5 × 10 mol L uranium
each sample. The analysis uncertainty is 10%, and the detection
threshold is 20 ppm.
The results obtained are expressed as ratios between partial
salt are electrolyzed using a potentiostat (Radiometer Voltalab
2
1) and applying a current of -1 mA during 27 h. The
VI
completion of the process, that is, total reduction of U into
U , is checked by using spectrophotometrical monitoring.
2
and N O detected. They permit one to calculate
pressures of H
the amount of gas molecules from the partial pressure, and from
2O pressure
2
IV
The pH of the medium, in which is dissolved the uranyl salt,
the solution and dead volumes of samples. The N
is in large excess and does not change notably during irradiation
variation less than 5% within 3 kGy).
-
1
-1
is adjusted to 0 with 1 mol L HCl and 1 mol L NaCl to
IV
12
stabilize U under atmosphere containing O
2
.
Actually, the
(
nitrate anions coming from the uranium salt have disappeared
VI
III
to form N
2
during the coulometric reduction of U into U ,
Results
Measurements of the Molar Extinction Coefficients of U
and U . The radiolytic oxidation of U into U is measured
IV
which is then oxidized into U as explained by Kolthoff et
1
3,14
IV
al.
To minimize the possible reactions under irradiation, no
VI
IV
VI
other molecule is added, for example, as stabilizer. The complex
IV
VI
forms of U and U are not clearly established under our
by observing the dose-dependent absorption spectra. As shown
VI
IV
conditions. It was reported that U in acetonitrile is complexed
by 6 Cl forming UCl
reported that U and U in the presence of 3 mol L Cl are
under the forms of U(H
in Figure 1a, U in NaCl/HCl is characterized by four peaks at
-
2- 15,16
6
,
but a recent EXAFS study in water
430, 495, 549, and 648 nm. As the uranium ions are highly
sensitive to complexation, the extinction coefficients of these
spectra should be accurately calibrated under the used conditions
IV
VI
-1
-
3
+
+
2 8 2 2 4
O) Cl and UO (H O) Cl , respec-
tively.17
of high Cl concentration. For each absorption peak, the values
-
IV
For dose-dependent absorbance measurements, when the
of the molar extinction coefficients of U in this medium were
IV
IV
coulometric preparation of U is over, the U solution (5 mM
determined. Experiments were done by using a set of solutions
at pH ) 0 and 2 mol L- Cl ) is inserted in a special cell divided
into two parts: the first one is a reservoir in which the sample
is stored during the irradiation, and the second one with a rubber
plastic septum is a spectrophotometric suprasil cell (1 cm). Both
parts are connected by a bridge in quartz, which allows the
system to be deaerated before irradiation and filled with the
1
-
of U at various concentrations in 1 mol L NaCl and 1 mol
L
IV
-1
-1
HCl. In Figure 1b, the absorbance of these solutions at each
selected wavelength is reported versus the concentration. The
absorbance is strictly proportional to the concentration in the
-1
range 0.5-10 mmol L (Figure 1b and inset). The molar optical
absorptivity was measured at different wavelengths correspond-
ing to the four maxima. The values are equal to (16 ( 1) L
selected atmosphere, the nitrous oxide (N
The concentration of N
O in pure water is 2.4 × 10 mol L ,
but at high ionic strength, such as in the solutions prepared in
2
O) in the present work.
-2
-1
-1
-1
-1
-1
2
mol cm at 430 nm, (29 ( 1) L mol cm at 495 nm, (21
1
-
-1
-1
-1
( 1) L mol cm at 549 nm, and (62 ( 1) L mol cm at
648 nm. During the irradiation, the concentration of U was
deduced from the absorbance at 648 nm where U does not
-
2
-1 18
IV
this work, it is only 1.5 × 10 mol L .
The γ-irradiation was performed using the panoramic 60Co
source at Chimie Physique laboratory, Orsay, with an activity
of 2400 Ci. The dose rate depends on the distance of the sample
to the 60Co source. In this method, the energy is absorbed by
the solvent where radiolytic oxidizing radicals are generated
with a controlled dose rate. The dose rate was measured using
VI
absorb. It is interesting to compare the corresponding extinction
coefficient to other ones, found in the literature. The value of
-1
-1
the extinction coefficient (62 L mol cm at 648 nm) deduced
-
1
-1
from Figure 1 is higher than the value 53 L mol cm as
obtained, for example, by spectrophotometry in the medium 1
mol L HBr aqueous solution. The difference is explained
by the specific complexation, because in the present solution
3
+
-1
19
the Fricke dosimeter with a radiolytic yield G(Fe ) equal to
-7
-1
3+
1
6.2 × 10 mol J and a molar extinction coefficient of Fe
-1 -1
-
3+
-
at 304 nm of 2160 L mol cm . The dose rate was corrected
2 8
the ions are complexed by Cl (U(H O) Cl ) instead of Br
IV
3+
17,20
by taking into account the density of the U solutions, which
is 1.04 kg L . The dose rate was equal to 45 ( 2 Gy min .
After each irradiation dose absorbed by the U solution, an
(UBr ) in the reported reference.
The intensity of the
-1
-1
VI
absorption band of U is known to be very low. Because of
the difficulty to estimate accurately the extinction coefficient
of U in such a low-concentration uranium solution, it was
IV
VI
absorption spectrum of the sample was registered. On the basis
IV
VI
IV
of the calibration of the absorbencies of U and U , the dose-
dependent concentrations of the ions are obtained.
evaluated by using the isosbestic point at 423 nm between U
VI
and U spectra (see below).