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Characterization and properties of Pleurotus mutilus fungalbiomass as adsorbent of the removal of uranium(VI)from uranium leachate
Meriem Mezaguer • Nour el hayet Kamel •
Hakim Lounici • Ziane Kamel
Received: 27 March 2012 / Published online: 3 July 2012
� Akademiai Kiado, Budapest, Hungary 2012
Abstract Removal and recovery of uranium from dilute
aqueous solutions by dead fungal biomass (Pleurotus muti-
lus) have been studied by biosorption. The parameters that
affect the uranium(VI) adsorption, such as: pH solution,
temperature, biomass particle size and speed of stirring have
been investigated and optimized. The experimental data
were analyzed using pseudo-first-order and pseudo-second-
order equations. The Freundlich and Langmuir adsorption
models have been used for the mathematical description of
the adsorption equilibrium. The maximum uranium bio-
sorption capacity has been calculated. The value obtained
(636.9 mg g-1) showed that P. mutilus is a good adsorbent.
Also, the chemical bands involved in uranium link have been
identified. We have applied this biosorption to actual waste
uranium leachate, the results are satisfactory and promising.
Keywords Pleurotus mutilus � Uranium � Leachate �Biosorption � Kinetics
Introduction
The removal of radionuclides such as uranium from
aqueous solutions, especially from contaminated sources, is
an important topic in environmental control.
Uranium is a radioactive element with many long lived
isotopes. The management of such radionuclide obeys to
the concepts of management of high-level radioactive
waste, as the removal/confinement principle as well as the
multi-concept barrier safety concept [24]. Thus, an ade-
quate solution for the disposal of uranium is to concentrate
and confine it in a sorbent matrix, before storing the waste
in a safe manner. This practice is usually employed in
bioremediation procedures in lands contaminated by
radioactive waste residues.
Many processes have been proposed for uranium(VI)
removal from industrial waste waters and radioactive
wastes. Chemical precipitation, ion exchange, and solvent
extraction are among the most commonly used methods,
each has its merits and limitation in application [17].
The biosorption is one of the promising technologies for
the removal of toxic metal from industrial waste and natural
waters. This technology has distinct advantages over con-
ventional methods. It is nonpolluting, easy to operate, offers
high efficiency of treatment of waste waters containing low
metal concentrations, and possibility of metal recovery [9].
Furthermore, the biosorption process offers a potential
benefit that is the low cost biomass, available in abundance
as sorbent; many biomasses remaining useless waste in
pharmaceutical industries [2, 12].
Pleurotus mutilus (noted P. mutilus) is a biomass used
by SAIDAL antibiotic complex at Medea, Algeria to pro-
duce a ‘‘pleuromutilin’’ antibiotic for veterinary use. Huge
quantities of residual P. mutilus biomass resulting from the
antibiotic extraction process are disposed after incineration.
So, we attempt to find an interesting use of this waste
through the removal of uranium from a radioactive effluent.
The adsorption of metals on P. mutilus has been per-
formed for copper and cyanide ferrous ions [3, 7]. The
biosorption of uranium on Pleurotus is not described yet.
However, several microorganisms are known to uptake
uranium by biosorption mechanisms [1, 4, 5, 21].
M. Mezaguer (&) � N. Kamel � Z. Kamel
Centre de Recherche Nucleaire d’Alger, 2 Bd Frantz Fanon,
B.P. 399, Alger-RP, Alger, Algeria
e-mail: [email protected]
H. Lounici
Ecole Nationale Polytechnique d’Alger, 10 Avenue Hassen Badi,
B.P. 182, El Harrach, Alger, Algeria
123
J Radioanal Nucl Chem (2013) 295:393–403
DOI 10.1007/s10967-012-1911-y
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In the present work, we try to validate valorization of
this waste biomass as a biosorbent for uranium(VI) by
investigating the influence of different experimental
parameters on uranium uptake, such as pH solution, tem-
perature, biomass particle size and speed of stirring.
For this purpose, we correlate different kinetic and
adsorption models, determine the corresponding kinetic
parameters, identify the chemical bonds involved in ura-
nium link on P. mutilus, and finally apply the results to
remove uranium from a laboratory radioactive waste.
Experimental
Biomass preparation
The crude biomass was washed with tap water, then with dis-
tilled water, and dried for 48 h at 65 �C in a Prolabo 250
steamroom. Then, it was powdered with a mortar and pestle set,
and was passed through sieves of different mesh sizes to get the
different particles sizes: (100–200 lm), (200–250 lm),
(250–315 lm), (315–400 lm), (400–500 lm), (500–630 lm)
and ([630 lm). All biomass fractions were stored at room tem-
perature before characterization and biosorption experiments.
Biomass characterization
The biomass pH was measured in ultra-pure water. The
biomass apparent density (qapp) was determined by pyc-
nometry using ethanol (Normapur, Prolabo) as a wetting
liquid. The residual humidity (H) was determined by suc-
cessive drying/weighing steps several times until the fun-
gus reached a constant weight.
The rate of organic matter (Rorg) was determined after
calcination at 600 �C for 2 h, and the rate of mineral matter
(Rmin) was deduced from the difference between the total
amount of biomass and the amount of organic matter. The
specific surface area (A) was measured by the BET method in
nitrogen at -196 �C using a Mastersizer-2000 instrument.
The microstructural characterization was determined by
Fourier transform infrared spectroscopy (FTIR) using a
Nicolet-380 instrument, and scanning electron microscopy
(SEM) using a Philips ESEM XL 30 FEG instrument. The
chemical composition of biomass was determined by a
Philips Magix-Pro X-ray fluorescence spectrometer (XRF).
Biosorption tests
Uranium(VI) solutions were prepared from a commercial
uranium nitrate: UO2(NO3)2�6H2O (Mallinckrodt Chemi-
cal). The pH of the solutions were adjusted to required
values by using either hydrochloric acid, HCl (Fluka,
37 %), or ammonia, NH4OH (Fluka, 25 %).
The adsorption experiments were carried out by batch
method. 0.5 g of biomass were contacted with 150 ml of
uranium solution under stirring at a speed of 315 rpm at
room temperature (&25 ± 1 �C). The supernatant was
separated by centrifugation at 104 rpm during 5 min.
Periodic samplings of the adsorbate are analyzed using a
Philips Magix-Pro XRF spectrometer, in order to assess the
uranium concentration in the solutions, 200 ll of solution
were analyzed. The accuracy of the method is about 3 ppm,
the relative error on measurements is 0.02 %, and the CSE
is 0.19 %. All the experiments were performed twice.
The amount of the biosorbed uranium per unit of bio-
mass (mg of U g-1 of dry biomass) at the equilibrium was
calculated using the following relation:
q ¼ C0 � Cð Þ � V
Wð1Þ
where C0 and C are respectively the uranium concentra-
tions (mg l-1) in the solution before and after the bio-
sorption, V is the solution volume (l), and W is the amount
of biomass (g).
Kinetic modeling
The kinetics of uranium uptake was modeled using the
pseudo first-order Lagergren’s equation and the pseudo
second-order Ho’s equation [13].
The pseudo-first-order sorption relation can be expres-
sed as follows:
1
qt¼ k1
q1
1
tþ 1
q1
ð2Þ
where q1 and qt are the amount of adsorbed uranium
(mg g-1) at the equilibrium time and at t time, respec-
tively; and k1 is the adsorption constant (min-1). The
values of k1 are calculated from the slope of the plot: 1/qt
versus 1/t.
The pseudo-second-order sorption relation can be
expressed as follows:
t
qt¼ 1
k2 � q22
þ 1
q2
t ð3Þ
where q2 is the amount of adsorbed uranium (mg g-1) at the
equilibrium, qt is the amount of the total solute adsorbed at
t time (mg g-1) and k2 is the kinetic constant (g mg-1 min).
A plot of t/qt versus t gives a linear relationship for the
applicability of the model. Both the intercept and slope of the
linear fit represent (k2) and (q2), respectively.
Equilibrium modeling
The adsorption curves were plotted by Langmuir and
Freundlich adsorption isotherms’ relations. These two
394 M. Mezaguer et al.
123
Page 3
equilibrium isotherm models are primarily used to interpret
the efficiency of metals sorption [28].
The Langmuir isotherm is applicable for hyperbolic
adsorption data. It is similar to the relation used for
Michaelis–Menten enzymatic kinetics, and describes the
single monolayer adsorption of metal ions to a finite
number of ligand sites on the cell surface.
The linearization of Langmuir isotherm can be expres-
sed as follows:
Ce
qe
¼ 1
qmax
1
KL
þ Ce
qmax
ð4Þ
where qe is the uranium concentration on the adsorbent at
the equilibrium (mg g-1). It is also called the equilibrium
adsorption capacity. Ce is the uranium concentration in the
solution at the equilibrium (mg l-1); qmax, is the maximum
adsorption capacity of the adsorbent (mg g-1); and KL is
the Langmuir constant or the separation factor.
The plot of Ce/qe versus Ce is a straight line, with the
slope (1/qmax) and the intercept (1/qmax KL).
Langmuir separation factor (RL) can be expressed in
terms of a dimensionless constant which is calculated using
the following mathematical relation:
RL ¼1
1þ KLC0
ð5Þ
The values of RL indicate the kind of adsorption:
– for RL [ 1: the isotherm is unfavorable,
– for RL = 1: the isotherm is linear,
– for 0 \ RL \ 1: the isotherm is favorable,
– for RL \ 0: the isotherm is irreversible
The linearization of Freundlich relation is:
ln qe ¼ ln KF þ1
nln Ce ð6Þ
where qe is the uranium uptake capacity at the equilibrium
(mg g-1), and Ce is the residual uranium concentration in
the solution (mg l-1). Kf represents Freundlich constant
which is a measure of the adsorption capacity. 1/n is the
adsorption intensity.
Results and discussion
Biomass characterization
Physical characteristics
The physical characteristics of biomass are given in
Table 1. These results show that biomass is mainly made
by organic matter. It is slightly acidic, low hygroscopic and
its specific surface area decreases with the rise of the
particles’ size.
Infrared spectroscopy
The FTIR analysis allows the identification of biomass
main functional groups, including those implied in the
biosorption phenomena.
The complex FTIR spectra of native biomass (Fig. 1)
shows the presence of R–NH2 aminogroups (amino acids,
proteins, glycoproteins, etc.), carboxylic acids groups (fatty
acids, lipopolysaccharides, etc.), sulfonates and phosphates
functional groups (Table 2).
SEM microscopic observations
The SEM observations of the biomass show its porosity,
(Fig. 2). The biosorbent particles have a rough porous
surface that favors the increase of the total specific area. In
addition, the micropores on the fungal biomass could
reduce the diffusion resistance at the biomass superficial
layer, and then facilitate the particles mass transfer because
of their large internal surface.
The biomass XRF analysis
The studied biomass is composed, in a large part (about
95 %), of organic matter, (see Table 3). The fungus con-
tains also about 3 % of nitrogen that is a protein constit-
uent, and a few amounts of phosphorous, potassium, zinc
and iron. These metals probably participate as cofactors for
several enzymes. It can be notes the presence of silicon,
which comes from the Decalite used for the biomass
filtration.
Optimization of the biosorption parameters
Effect of pH on uranium biosorption
The pH level of solution plays an important role in the
biosorption of uranium on biomass. It has an effect on both
the speciation of uranium in the aqueous solution and the
binding sites located on the biomass surface [15].
Table 1 Physical characteristics of biomass
Particle
size (lm)
pH H (%) qapp
(g cm-3)
Rorg
(%)
Rmin
(%)
A (m2 g-1)
100–200 6.20 2.4 1.32 95.8 4.2 0.129
200–250 6.25 2.4 1.32 95.8 4.2 0.120
250–315 6.26 2.4 1.30 95.8 4.2 0.108
315–400 6.23 2.4 1.28 95.8 4.2 0.090
400–500 6.20 2.4 1.27 95.8 4.2 0.068
500–630 6.25 2.4 1.25 95.8 4.2 0.043
C630 6.25 2.4 1.22 95.8 4.2 0.030
Characterization and properties of Pleurotus mutilus 395
123
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Uranium loading by P. mutilus increased with increasing
pH from 2 to 5 (Fig. 3) exhibiting a maxima of 250 mg g-1
at pH 5. This result agrees with those reported in several
studies on biosorption of uranium [5, 11, 29].
At pH values higher than 5, the solubility of metal
complexes decreases, provoking a bulk precipitation of
these species, which become easily removable from the
solution by filtration [6].
For low pH, the uranium biosorption decreases because
of the abundance of H? and H3O? ions, which compete
with other ions, as uranyl, for the binding sites of the
biomass surface [22]. When the pH increase (at pH 5), this
phenomenon attenuates, and many ligands on the biomass
surface can be observed, such as: carboxyl, amino and
other phosphate groups, characterized by pK values in the
range of 3–5 [14].
503,72
594,48
676,59732,77840,82
901,32935,89970,47
996,40
1061,221108,76
1167,481251,38
1333,49
1376,71
1451,32 1644,66
1726,02
1737,831795,92
2716,45
2840,00
2924,76
3191,84
3451,14
3541,90
10 15
20
25
30
35
40
45
50
55
60
65
70
75
80
85
90
95
%Transmittance
500 1000
1500 2000
2500 3000
3500 4000
Nom
bre d'onde (cm-1)
Fig. 1 Infrared spectra of P. mutilus
Table 2 The infrared absorption bands and their corresponding
possible groups
Wave
number
(cm-1)
Functional groups Localization in the cell
wall
3,200 Primary and
secondary amine
N–H Amino acids
Peptide bonds
(peptidoglycan)
N-acetylglucosamine
N-acetylmuramic
2924.76 Aliphatic chain C–H CH3 of peptidoglycan
Ch3 of teichoic acid2,840
2722.70
1737.83 Carboxylic groups C=O Tetrapeptide mureic
Proteins
1726.02
1648.98 RNH2 (primary
amine)
N–H Peptide bonds
Primary and
secondary amide
Peptidoglycan
Proteins
N-acetylglucosamine
N-acetylmuramic
1451.32 Tertiary amide C=O Proteins
1377.08 RNH2 (primary
amine)
N–H Peptide bonds
Primary and
secondary amid
Proteins
N-acetylglucosamine
N-acetylmuramic
1254.76 Primary amine
R–NH2
C–N Amino acid
1167.48 R–CH2OH
(primary OH)
C–OH N-acetylglucosamine
N-acetylmuramic
997.71 Carbohydrate C–O–C N-acetylglucosamine
972.40
840.68 Phosphohydrate C–O N-acetylmuramic
C–O–P Proteins
P–O–P
C–O–P/
P–O–P
739.05 Thiol C–SH2 Radicals of cysteine and
methionine
590.31 –C–S–
S–C
Intra-protein SS bridge
between two cysteic
residues.
507.85 R–C–O–P–(OOH)
–O–C–R0O–P–O Phosphate ester
Disulfure S–S Phospholipid
Teichoic acids
Intra-SS-protein bridge
between two cysteine
residues
396 M. Mezaguer et al.
123
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Effect of the biomass particle size on uranium biosorption
The greatest amount of adsorbed uranium is 250 mg g-1,
at the adsorption equilibrium. It is reached for a biomass
granulometry of 250–315 lm (Fig. 4).
The lowest value of the maximum rate of adsorbed
uranium is about 150 mg g-1. It is obtained for particles’
grains sizes greater than 630 lm.
The decrease of the particles size favors the uranium
transfer by increasing the contact between the biomass
external surface and uranium particles [16].
It can be noted that the smallest biomass size fractions
of 100–200 and 200–250 lm agglomerate in a pasty shape
in the liquid medium. This causes the reduction of the
biomass surface which is in contact with the solution, and
thus the rate of uranium adsorption is reduced.
Effect of stirring speed on uranium biosorption
The uranium adsorption capacity varies in the same order
with the stirring speed (Fig. 5). The maximum sorption
capacity was found for a stirring speed of 315 rpm.
It should be noted that, the use of an agitation higher
than 315 rpm causes a dispersion of biomass on the walls
of the container, which distorts the experience.
The increase in the stirring speed favors the diffusion of
uranium into the boundary layer adsorption which becomes
very thin and the diffusion coefficient of adsorbed species
increases. Parab et al. [20], reported that stirring speed
varies in the same order with the uranium adsorption on the
biomass.
Table 3 The biomass chemical composition determined by XRF
Element Composition (%)
Organic matter 95.8
N 3.364
Mg 0.034
Al 0.065
Si 0.254
P 0.216
S 0.042
Cl 0.006
K 0.163
Ca 0.025
Mn 0.001
Fe 0.009
Zn 0.002
Na 0.020
Fig. 2 SEM micrographs of P. mutilus (G 9500)
Fig. 3 Effect of initial solution pH on uranium biosorption (W =
0.5 g, Ci = 1,000 ppm, V = 150 ml, temperature = 25 ± 1 �C, stir-
ring speed = 315 rpm and ø = 315–400 lm)
Fig. 4 Effect of the biomass particle size on uranium biosorption
(pH = 5, W = 0.5 g, Ci = 1,000 ppm, V = 150 ml, tempera-
ture = 25 ± 1 �C, stirring speed = 315 rpm)
Characterization and properties of Pleurotus mutilus 397
123
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Effect of temperature on uranium biosorption
The maximum uranium adsorption capacity is obtained at a
temperature of 15 ± 2 �C (Fig. 6). The temperature
decrease favors the uranium adsorption on biomass. Thus,
the biosorption process is exothermic in nature.
Many authors have reported that the decrease in tem-
perature favors the adsorption of cationic species on the
biomass [16, 17, 25].
Effect of initial uranium concentration on biosorption
The uranium maximum adsorption capacity increases with
the uranium concentration in the solution, from 183 to
583 mg g-1 (Fig. 7). However, the rate of adsorbed
uranium decreases with the uranium starting concentration
(Fig. 8).
It can be deduced that for uranium low concentrations,
the ratio between the number of uranium free particles in
the solution and the available surface area for biosorption is
small. Consequently, the adsorbed uranium fraction is
independent of the uranium initial concentration in the
solution. However, for very high uranium starting con-
centrations, the number of sorption sites is lower than the
total uranium particles. Consequently, a part of these par-
ticles remains free in the solution and the fungus surface
saturates.
The kinetic modeling
It appears that the kinetic data can be better described by
Ho’s pseudo-second-order relation (Fig. 9b) comparatively
to Lagergren’s pseudo first-order relation (Fig. 9a).
This model (pseudo-second-order) has been described in
the literature as suitable for the adsorption in the case of
several biosorbents [1].
The equilibrium modeling
The variation of the equilibrium adsorption capacity qe as a
function of the uranium starting concentration is depicted
on Fig. 10. We can deduce that the experimental maximum
adsorption of uranium on P. mutilus is about 600 mg g-1.
The overall results show that both adsorption models are
applicable to describe data for the equilibrium adsorption
of uranium on P. mutilus. The Langmuir model (Fig. 11) is
more accurate than that of Freundlich (Fig. 12). Langmuir
Fig. 5 Effect of stirring speed on uranium biosorption (pH = 5,
W = 0.5 g, Ci = 1,000 ppm, V = 150 ml, temperature = 25 ± 1 �C,
and ø = 315–400 lm)
Fig. 6 Effect of temperature on uranium biosorption (pH = 5,
W = 0.5 g, Ci = 1,000 ppm, V = 150 ml, stirring speed = 315 rpm,
and ø = 315–400 lm)
Fig. 7 Effect of initial concentration on uranium biosorption
(pH = 5, W = 0.5 g, V = 150 ml, stirring speed = 315 rpm, tem-
perature = 15 �C and ø = 250–315 lm)
398 M. Mezaguer et al.
123
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and Freundlich parameters characterizing adsorption
capacity of P. mutilus are given in Table 4.
The Langmuir constant, RL, are in the range 0–1
(Fig. 13). Thus, the isotherm is favorable, indicating a
beneficial uranium biosorption on biomass.
The Langmuir theoretical maximum adsorption of ura-
nium on P. mutilus is of 636.94 mg g-1, which is higher
than experimental value.
Similar results are reported by Akhtar et al. [1] for
uranium adsorption on Trichoderma harzianum fungus,
which have reported 612 mg g-1 of adsorbed uranium.
Bhainsa and D’Souza [5] studied the biosorption of ura-
nium on Aspergillus fumigatus and report a uranium
adsorption rate of 423 mg g-1.
(a)
(b)
Fig. 9 The linearized kinetic models of the uranium uptake on P.mutilus. a Pseudo-first-order, b pseudo-second-order
Fig. 11 The Langmuir adsorption isotherm for the uranium sorption
onto P. mutilus
Fig. 8 Variations of the rate of uranium adsorbed on P. mutilusversus the initial uranium concentration in the solution
Fig. 10 Variation of the equilibrium adsorption capacity qe versus
the initial uranium concentration in the solution
Characterization and properties of Pleurotus mutilus 399
123
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Application: separation of uranium from a leachate
by adsorption on P. mutilus
Chemical characterization of the uranium leachate
In this study we used a uranium leachate resulting from the
experience of extracting uranium from ore.
The leachate chemical composition, measured by XRF
analysis, shows that it contains about 830 ppm of uranium,
7190 ppm of sulfur coming from the sulfuric acid used in
the extraction process of uranium, 800 ppm of phosphorus,
370 ppm of iron, 450 ppm of aluminum and 340 ppm of
potassium (Table 5). These last elements probably come
from the ore rocks, which are rich in these elements.
The measured value of the leachate pH was equal to 1.
Increasing the pH of the leachate up to 5 was not feasible.
In the following part, only a solution of leachate with pH 2
is used.
When the pH is adjusted to the value of 2, there is a
precipitation of the elements.
The amount of uranium in the solid phase was deduced
from the uranium concentration in the leachate after
precipitation.
It can be noticed that almost 40 % of uranium was
precipitated along with other elements (Table 5).
Sodium reduces from 230 to 39 ppm after adjusting the
pH to 2. One can deduce that this alkali element precipi-
tates simultaneously with uranium.
Sodium is often a charge compensator in some chemical
uranium forms as lanthanides/actinides phosphates, which
have greater valences, and thus co-precipitate with alkali
elements [19]. Further analytical investigations are needed
to confirm this assumption.
Fig. 13 Variations of the separation factor (RL) versus the initial
uranium concentration in the solution
Table 4 The calculated kinetic parameters from the Langmuir and
Freundlich isotherms for the uranium adsorption by P. mutilus
Isotherm
model
qmax
(mg g-1)
KL
(l mg-1)
n KF
(mg g-1)
Correlation
coefficient r2
Langmuir 636.9 0.003209 – – 0.99
Freundlich – – 2.80 36.64 0.95
Table 5 The chemical composition in ppm of the uranium leachate
at pH 1, pH 2 and after adsorption
Element pH 1 leachate pH 2 leachate After adsorption
U 830 500 0
Ti 68 1.31 1
V 10 5.34 5.3
Cr 10 5.88 6.32
Mg 14 11.13 90
Cu 17.1 13.4 11
Y 17.1 16.49 15.47
Na 230 39 50
Mn 170 10 11.04
Al 460 350 400
Si 29 20 30
K 340 210 190
Ca 68 60 70
P 800 350 398
Fe 370 90 90
Ni 4.12 4.11 4.11
S 7,190 7,000 6,910
Fig. 12 The Freundlich adsorption isotherm of the uranium sorption
onto P. mutilus
400 M. Mezaguer et al.
123
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The precipitates were separated by filtration and the
filtrate containing the residual uranium has been used for
the adsorption test.
Separation of uranium from the leachate by biosorption
The biosorption tests are conducted in the optimum con-
ditions except for pH (pH = 2, particle size: 250–315 lm,
a temperature of 15 �C and stirring speed of 315 rpm).
After adding the biosorbent to the filtered leachate, the
concentration of uranium was measured until it becomes
negligible. One can deduce that the total amount of ura-
nium in the leachate was shared between the precipitate
and the biosorbent.
The uranium adsorption capacity increases to a value
of 125 mg g-1 after 6 h of biosorption, and then tends
to stabilize at about 24 h (Fig. 14). This value
(&125 mg g-1) corresponds to 100 % of uranium
adsorption. This is confirmed by analyzing the aliquot by
XRF, no presence of uranium pick is noted. The pH of the
leachate after being treated with the biomass was around
1.7–1.8. The acidic particles, as H3O?, are participating to
the adsorption process.
Moreover, a partial absorption of copper, potassium and
sulfur from the solution can be observed (Fig. 15). For
sulfur, its concentration value decreases from 7,000 to
6,910 ppm.
However, concentrations of magnesium, sodium, alu-
minum, sulfur and phosphorus rise at the end of the bio-
sorption test. Concentrations of ions remaining in solution
after extraction are given in Table 5.
This unexpected result may be explained by the fact that
P. mutilus naturally contains several metals, which may be
released from the biomass under the effect of an acidic pH
(pH = 1 and 2 of the leachate).
Vijayaraghavan et al. [27] has reported that acid washes
of the biomass provoke a release of many metals in the
leachate. H3O? species replace the metallic cations in their
binding sites and the released cations become in a free state
in the solution.
FTIR analysis after uranium biosorption
Comparison of biomass FTIR spectra before and after
uranium biosorption shows peaks’ transformations, due to
the cationic exchanges (Fig. 16a). The disappearance of the
peak at 1,770 cm-1 is observed corresponding to the C=O
bond lengthening of the COOH group belonging to the
tetrameric peptide or protein. The appearance of a peak at
1,546 cm-1 shows the stretching of both primary and
secondary amines, belonging to N-acetylglucosamine or N-
acetylmuramic, the peptide bonds of peptidoglycan or
proteins, respectively. Also, the peaks located at 587.1 and
506.57 cm-1 move to the values of 558.47 and
463.62 cm-1, respectively. These absorption frequencies
correspond either to the elongation of the O–P–O phos-
phoric ester bond or the S–S links. The phosphoric ester
bonds belong to phospholipids or teichoic acids, and the
disulphide S–S bonds belong to protein disulfide bonds
between two cysteines. The peak located at 678.37 cm-1 is
moved to 640.79 cm-1 corresponding to the C–S elonga-
tion of both CS–H2 and S–S–C groups, belonging to the
cysteine or methionine intra-protein bonds between two
cysteines.
Similar results have been reported in the literature, and
the involvement of these functional groups in the uranium
and cadmium biosorption has been described [8, 10, 18,
26].
Fig. 14 Variations of the uranium adsorption capacity from the
leachate on P. mutilus (pH = 2, ø = 250–315 lm, temperature of
15 �C, and stirring speed of 315 rpm)
Fig. 15 Chemical composition of the uranium leachate (ppm) before
and after adsorption
Characterization and properties of Pleurotus mutilus 401
123
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However, the peaks in 4,000–2,000 cm-1 frequency
region are unchanged (Fig. 16b). This area highlights the
CH adsorption bonds where CH groups do not contribute to
the binding of uranium onto the biomass. This non con-
tribution of CH linked in the adsorption of cadmium and
chromium is known for Hylocomium splendeus [23].
Conclusions
In this study, we have investigated the adsorption of ura-
nium on P. mutilus fungus, a by-product of the Algerian
pharmaceutical industry. The biomass has been prepared
and characterized. The uranium biosorption optimized
parameters were fixed to: pH 5, at 15 �C, speed of stirring
at 315 rpm and the biomass particle size in the interval of
250–315 lm.
The kinetic modeling of the adsorption is governed by a
pseudo second order model. The application of Langmuir
model gives a uranium maximum theoretical adsorption
capacity of 637.9 mg g-1.
The experiences of uranium separation from an actual
leachate at pH 5 failed and this feature has restricted us to
work at pH 2. Nevertheless, the result of separation at pH 2
was satisfactory (100 % adsorption of uranium from the
solution). But there is a partial adsorption of some elements
and release of the elements contained in the biomass in
middle.
463,62
558,47
640,79
1546,32
506,57
587,10
678,37
1770,02
15
20
25
30
35
40
45
50
55
60
65
70
75
80
85
90
95
100
%Transmittance
600 800
1000 1200
1400 1600
1800 2000
Nom
bre d'onde (cm-1)
(a)
Fig. 16 The infrared spectra of P. mutilus before (top) and after
(down) the uranium biosorption. a frequency region of
2,000–500 cm-1, b frequency region of 4,000–2,000 cm-1
15
20
25
30
35
40
45
50
55
60
65
70
75
80
85
90
95
100%Transmittance
2200 2400
2600 2800
3000 3200
3400 3600
Nom
bre d'onde (cm-1)
(b)
Fig. 16 continued
402 M. Mezaguer et al.
123
Page 11
The FTIR analysis of biomass, before and after
adsorption, has highlighted the involvement of carboxylic,
amine, phosphoric and sulfuric bonds, in the adsorption
phenomenon.
These preliminary results are very promising showing
great perspectives in application of the P. mutilus as bio-
sorbent for uranyl ions in radioactive wastewater treatment
processes with a sustainable technology.
Acknowledgments We acknowledge Doctor Abed Belkassemi
from SAIDAL Medea for providing us biomass samples. We grate-
fully acknowledge the contribution of Doctor Salah Chegrouche from
Nuclear Research Centre of Draria (in Algiers) for his useful help.
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