radioactive fallout cesium in sewage sludge ash produced after the fukushima daiichi nuclear...
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Radioactive fallout cesium in sewage sludge ashproduced after the Fukushima Daiichi nuclearaccident
Naofumi Kozai*, Shinichi Suzuki, Noboru Aoyagi, Fuminori Sakamoto,Toshihiko Ohnuki
Japan Atomic Energy Agency, 2-4 Shirane, Shirakata, Tokai-mura, Naka-gun, Ibaraki 319-1195, Japan
a r t i c l e i n f o
Article history:
Received 22 August 2014
Received in revised form
17 October 2014
Accepted 18 October 2014
Available online 29 October 2014
Keywords:
Sewage sludge ash
Cesium-137
Fukushima
Dissolution
Iron
Silicate
* Corresponding author.E-mail address: [email protected]
http://dx.doi.org/10.1016/j.watres.2014.10.0380043-1354/© 2014 Elsevier Ltd. All rights rese
a b s t r a c t
The radioactive fallout cesium (137Cs) in the sewage sludge ashes (SSAs) produced in Japan
after the Fukushima Daiichi Nuclear Accident was tested. Five samples of SSAs produced in
2011 and 2012 were tested. Two of the samples contained 137Cs (23 and 9.6 kBq/kg,
respectively) above the radioactivity criterion (8 kBq of radioactive Cs/kg of solid) for
controlled landfill disposal in Japan. The mineral components of SSA are roughly divided
into two groups: an HCl-soluble phase mainly composed of phosphates and oxides; and
silicates, including quartz, feldspar, and clay. Both phases contained 137Cs. The majority
(up to 90%) of 137Cs was contained in the HCl-soluble phase. Among the HCl-soluble sub-
phases, Fe-bearing phases that were probably iron oxides were mainly responsible for 137Cs
retention. No positive evidence was obtained that showed that phosphate-bearing phases,
which were included most in SSAs along with the silicate phase, retained 137Cs. Pre-
pulverizing SSAs and heating them at 95 �C in a 6 M or a concentrated aqueous HCl was
the most effective method of dissolving the HCl-soluble phase. The radioactivity concen-
trations of 137Cs in all the HCl-treatment residues were below the radioactivity criterion.
This residue was mostly composed of silicates. After static leaching tests of the residue at
60 �C for 28 days, no 137Cs was detected in simulated environmental water leachates (pure
water and synthetic seawater), demonstrating that 137Cs in the residue is very stably
immobilized in the silicates.
© 2014 Elsevier Ltd. All rights reserved.
1. Introduction
In March 2011, huge quantities of radionuclides were emitted
into the atmosphere by the consecutive explosions in the re-
actors and reactor buildings at the Fukushima Daiichi Nuclear
Power Plant (FDNPP). The emission of radionuclides began on
(N. Kozai).
rved.
March 12 and the total emission of 137Cs into the atmosphere
was estimated to be in the range of 10e36 PBq (Chino et al.,
2011; Morino et al., 2011; Stohl et al., 2012). The radioactive
Cs fallout was dispersed from the FDNPP into the ocean and
across large areas of Japan, including the Tohoku and north
Kanto regions (Fig. S1 in the Supplementary content) (Chino
et al., 2011; Kawamura et al., 2011). The soil, animals, plants,
wat e r r e s e a r c h 6 8 ( 2 0 1 5 ) 6 1 6e6 2 6 617
architectural structures, and natural water in these regions
were contaminated with radioactive Cs (Koarashi et al., 2012;
Kozai et al., 2012; Shibata et al., 2012; Nakanishi et al., 2013;
Tanaka et al., 2013; Saegusa et al., 2014; Sakai et al., 2014).
Subsequently, rainwater has dissolved some of the radio-
active Cs from contaminated objects or washed the contam-
inated objects containing radioactive Cs away. Some of the
radioactive Cs has been discharged into combined sewerage
systems, where rainwater and sewage are collected together
and conveyed to sewage treatment plants. The wastewater is
purified by physical screening or sedimentation to remove
solids, and then by removing soluble and fine suspended
pollutants through biological processes. These treatments
produce sewage sludge. In Japan, sewage sludge is dried and
incinerated at 800e850 �C, and the end product is called
sewage sludge ash (SSA). These treatment processes reduce
the sewage sludge to SSA that is several hundredths of the
original volume of the sludge, thereby enriching the radioac-
tive Cs in SSA. Since the Fukushima Daiichi accident, highly
concentrated radioactive Cs has been detected in the SSAs
produced at many sewage treatment plants in Japan. The
concentration of radioactive Cs varies considerably among
different plants and production dates. The highest reported
concentration is 4 � 105 Bq/kg (in dehydrated sludge) as of
October 28, 2011 (the Ministry of Land, Infrastructure,
Transport and Tourism of Japan, 2011).
SSA, which is produced daily in large quantities, had been
used before the Fukushima Daiichi accident mainly as raw
material for cement and was not disposed of in landfills.
However, due to the accident, reuse of contaminated SSA in
the cement industry is no longer possible due to the high
radioactivity. The contaminated SSA is now being stored in
sewage treatment plants.
Currently, it is intended that the contaminated SSAswill be
buried in controlled or strictly controlled landfill sites based
on a radioactivity criterion (8 kBq of radioactive cesium per kg
of solid) (Ministry of the Environment, 2011). It may be also
possible to reduce the radioactivity of SSAs to achieve safe,
readily controlled landfill disposal. However, for the imple-
mentation of any of these options, it is essential to elucidate
the physical and chemical properties of the radioactive Cs in
SSAs, because currently, very little is known this.
To contribute to establishing themethodology for reducing
the radioactivity of SSAs and their subsequent safe landfill
disposal, we investigated SSAs contaminated with radioactive
Cs from the FDNPP. The maximum radioactivity concentra-
tion of 137Cs in the SSA tested in this study is 23 kBq/kg. This
Table 1 e Sampling site, date, and radioactivity concentration
Sewage treatment plant Date ofoccurrence
Rad
Iwaki city central sewage treatment plant,
Iwaki, Fukushima
May, 2011
Iwaki city central sewage treatment plant,
Iwaki, Fukushima
May, 2012
Teganuma sewage treatment plant, Abiko, Chiba June, 2011
Teganuma sewage treatment plant, Abiko, Chiba May, 2012
Nakakuji sewage purification center,
Hitachinaka, Ibaraki
May, 2012
value is high for radioactivity, although themolality of 137Cs is
only 0.052 nmol/kg. Therefore, it is impossible to analyze the
chemical states of 137Cs directly in the SSAs. The properties of137Cs in the SSAs were analyzed in terms of the static leaching
and acid-dissolution behaviors of 137Cs and the major
component elements of the SSAs. The effect of pulverizing
SSAs on acid-dissolution of 137Cs was also examined to
develop a method to reduce radioactivity effectively.
2. Materials and methods
2.1. Sewage sludge ash
Five samples of SSA generated in 2011 and 2012 were collected
from three sewage treatment plants (Table 1 and Fig. S1 in the
Supplementary content). The SSA samples were fine brown or
reddish-brown powders. We tested as-incinerated SSAs and
pre-pulverized ones. As-incinerated SSA samples were used
with no pretreatment except being dried at 30 �C to remove
the moisture that had been added to SSAs for storage at
sewage treatment plants. Pre-pulverized SSA samples were
prepared by an automatic mortar grinder with an agate
mortar or a planetary ball mill (PM200, Retsch GmbH, Ger-
many) with a zirconia grinding jar and 3-mm zirconia balls.
2.2. Chemicals
All reagent solutions used in the present study were prepared
using ultrapure water (18.2 MU cm�1) and reagent-grade
chemicals.
2.3. Static leaching and dissolution experiments
The leaching and dissolution properties of 137Cs from the SSA
samples were examined in the following two experiments.
2.3.1. Static leachingStatic leaching behaviors of 137Cs were investigated in pure
waterandsyntheticseawater. For thisexperiment, Iwaki’11and
Teganuma’11 samples, which had the highest and the second
highest radioactivity concentrations of 137Cs, respectively,were
tested. The SSA sample (2.00 g) was added to purified water
(100mL) or synthetic seawater (NaCl 25 g/L, MgCl2$6H2O 11 g/L,
CaCl2$2H2O 1.4 g/L) in a plastic bottle, and the bottle was left to
stand at 25 or 60 �C without agitation. The static leaching ex-
periments were performed for up to 28 days. After the
of SSAs.
ioactivity concentrationof 137Cs kBq/kg
Specific surfacearea m2/g
Abbreviation
23 1.3 � 102 Iwaki’11
6.5 e Iwaki’12
9.6 1.3 � 102 Teganuma’11
2.8 e Teganuma’12
6.8 e Nakakuji’12
wat e r r e s e a r c h 6 8 ( 2 0 1 5 ) 6 1 6e6 2 6618
experiment, the liquid phase was collected by centrifugation,
passed through a filter with pore size 0.45 mm, and the radio-
activity of 137Cs in the liquid phase was determined.
2.3.2. Dissolution in various reagentsDissolution behaviors of 137Cs and the major component ele-
ments (Na, K, Mg, Ca, Al, Fe, Si, and P) of SSAs in various re-
agent solutions were investigated. The dissolution of 137Cs
was tested in a larger scale experiment (initial weight of SSA,
1.00 g) and elemental analysis was carried out a smaller scale
experiment (initial weight of SSA, 0.100 g). The SSA sample
was soaked in a reagent solution in a plastic bottle at a solid/
liquid ratio of 1/200 g/mL. The bottle was left to stand at 25, 60,
or 95 �C for up to 24 h without agitation. The solid phase was
separated from the liquid phase by centrifugation (10,000 rpm,
5 min), washed with purified water three times, and dried at
60 �C. In the larger scale experiment, the radioactivity of 137Cs
in the solid phase and the dry weight of the solid phase were
determined before and after the experiment. In the small-
scale experiment, the liquid phase and all of the rinsing so-
lutions were collected, combined, diluted with pure water,
and passed through a filter with a pore size of 0.45 mm to
determine the concentrations of themain dissolved elements.
Aqueous 0.1 and 1 M citric acid, 0.1 and 1 M sodium citrate,
0.1MEDTA$2Na, 0.5Mand saturated (ca. 1M) oxalic acid, nitric
acid at various concentrations, hydrochloric acid at various
concentrations, andconcentratedhydrofluoric acidwereused.
2.4. Analysis
The radioactivity of 137Cs was determined by a g-ray spec-
trometer with a germanium detector (ORTEC GEM-15180,
Advanced Measurement Technology Inc., USA). The
Table 2 e Elemental compositions of SSAs.
Iwaki'11 Iwaki'12 Teganuma'11 Teganuma'12 Nak
SiO2 24.6 29.6 23.3 25.5
Al2O3 11.3 13.1 11.6 12.0
P2O5 24.7 20.3 32.3 28.5
MgO 2.8 2.4 3.1 2.7
CaO 13.9 11.5 9.7 11.9
Fe2O3 13.7 14.9 11.9 12.2
Na2O 1.2 1.1 0.7 0.4
K2O 2.3 2.2 2.6 2.8
TiO2 1.1 1.1 0.8 1.1
NiO 0.0 0.0 0.0 0.0
CuO 0.3 0.3 0.2 0.2
MnO 0.3 0.4 0.2 0.1
ZnO 0.6 0.6 0.8 0.5
SrO 0.1 0.1 0.1 0.1
ZrO2 0.0 0.0 0.0 0.0
BaO 1.3 0.8 1.6 0.7
PbO 0.0 0.1 0.0 0.0
As2O3 0.0 0.0 0.0 0.0
SO3 1.5 1.3 1.4 1.3
Cl 0.2 0.1 0.0 0.0
Total
weight %
100.0 99.9 100.2 100.0
a Treated at 60 �C for 24 h.
elemental compositions of SSA samples were determined by a
wavelength dispersive X-ray fluorescence (XRF) spectrometer
(Primus II, Rigaku Corp., Japan). The BET surface areas were
measured by a surface area analyzer (Nova 1000e, Quantach-
rome Instruments, USA). Concentrations of metals in the
liquid phase were determined with an inductively coupled
plasma optical emission spectrometer (ICP-OES; 720, Agilent
Technologies, Inc., USA), an inductively coupled plasmamass
spectrometer (NexION 300X, PerkinElmer, Inc., USA), and an
atomic absorption spectrometer (AA-6200; Shimadzu Corp.,
Japan). Powder X-ray diffraction (XRD) data were obtained
with an X-ray diffractometer (Ultima IV, Rigaku Corp.). The
surface morphology of the solid phases were observed by
scanning electron microscopy (SEM; Phenom ProX, Phenom-
World, Netherlands, and JSM-7800F, JEOL, Japan) with an en-
ergy dispersive X-ray (EDX) analysis system.
3. Results
3.1. Chemical and mineral compositions of as-incinerated SSAs
Table 2 shows the elemental compositions of as-incinerated
(original) SSA samples. Si and P were the most abundant ele-
ments contained in these SSAs, and Al, Ca, and Fe were the
second most abundant. The elemental compositions of the
samples varied according to the time and location of pro-
duction, and the Si and P oxide content showed maximum
differences between samples of 5% and 12%, respectively.
XRD patterns of the SSA samples are shown in Fig. 1.
Although the relationship between peak intensities were
different among the samples, most of the major diffraction
akuji'12 Iwaki '11 residue after6 M HCl treatmenta
Teganuma '11 residue after6 M HCl treatmenta
27.4 80.8 85.5
11.6 8.3 5.5
27.1 0.5 1.3
2.8 0.7 0.6
10.5 2.4 1.1
11.4 2.5 1.7
0.9 0.9 0.5
3.5 2.2 2.0
1.1 1.2 1.5
0.0 0.0 0.0
0.2 0.0 0.0
0.3 0.1 0.0
0.5 0.2 0.0
0.1 0.0 0.0
0.0 0.0 0.0
1.4 0.0 0.0
0.0 0.0 0.0
0.0 0.0 0.0
1.0 0.1 0.1
0.1 0.0 0.0
100.0 99.9 100.0
wat e r r e s e a r c h 6 8 ( 2 0 1 5 ) 6 1 6e6 2 6 619
peakswereobserved inallof thesamples, showing that theSSAs
were composed of similar minerals. The mineral phases of the
samples were divided into two groups according to their solu-
bility in aqueous HCl. The major minerals soluble in aqueous
HCl were expected to be iron oxides (hematite, maghemite,
goethite), and various phosphates of aluminum, calcium, and
iron (Al(PO3)3, rodolicoite, brushite, whitlockite, wyllieite). No
XRD peaks of simple aluminum oxides (e.g., alumina, gibbsite)
were observed. No diffraction peaks for S-bearing phases were
present in the XRD patterns; however, the presence of fine pre-
cipitates of S-bearing phases containing Ca or Ba, probably cal-
cium sulfate and barium sulfate, was confirmed by SEM-EDX
analysis. The major minerals insoluble in aqueous HCl were
quartzandfeldspar. Inallof theXRDpatterns,aweakdiffraction
peak was observed at 9.4e9.5� (d¼ 0.93e0.94 nm) and this peak
may be the strongest peak for talc. This talc may have been
formedby the incinerationofsewagesludge,because talc canbe
synthesized at several hundred degrees Celsius from silicon
dioxide and magnesium (Dumas et al., 2013; Takahashi et al.,
1994), although the talc is more likely to originate from addi-
tives in paper flushed into sewers. XRD peaks of other clay
minerals were not observed.
3.2. Static leaching behavior of 137Cs from as-incinerated SSAs
Fig. 2A shows the time course of the leaching behavior of 137Cs
from the Iwaki’11 sample into pure water and synthetic
Fig. 1 e XRD patte
seawater. At 25 �C, the percentages of the leached 137Cs
reached constant values in 7 days in both pure water and
synthetic seawater. After 28 days, 0.5% and 3% of the 137Cswas
leached into pure water and synthetic seawater, respectively
(Table 3). At 60 �C, the percentages of the leached 137Cs in pure
water reached constant values (ca. 1%) in 1 day, whereas that
leached into the synthetic seawater increased with time and
did not reach a constant value (ca. 6% at 28 days). These re-
sults indicate the presence of loosely bound (water-soluble
and exchangeable) 137Cs in SSA. After 28 days in the static
leaching test for the Teganuma’11 sample at 25 �C, 2% and 3%
of 137Cs were leached in pure water and synthetic seawater,
respectively. These values are similar to those for the Iwaki’11
sample.
Fig. 2B and Figure S2AeC in the Supplementary content
show the time course of the concentrations of the main
metallic elements (Na, K, Mg, Al, P, Ca, and Fe) leached from
the Iwaki’11 sample into pure water and synthetic seawater.
The Na, Mg, and Ca that leached into synthetic seawater were
not measured because the synthetic seawater originally con-
tained these elements at high concentrations. The concen-
trations of Fe and Al leached into the synthetic seawater were
below the detection limits of the ICP-OES instrument
(10e20 ppb). Therefore, only the results for leached K and P are
shown in Figs. 2B and S2C, respectively. The characteristic
time course of the leaching behavior of 137Cs (Fig. 2A) was in
good agreement with that of K (Fig. 2B). Although the leaching
behaviors of Na and Ca in purified water (Fig. S2A) were
rns of SSAs.
Fig. 2 e Time course of leaching behaviors of the 137Cs and K of as-incinerated Iwaki '11 sample in purified water (PW) and
synthetic seawater (SSW). (A) Percent fraction of the amount of leached 137Cs with respect to the initial amount of 137Cs in
the as-incinerated sample, and (B) the concentration of K in leachates.
wat e r r e s e a r c h 6 8 ( 2 0 1 5 ) 6 1 6e6 2 6620
similar to that of 137Cs (Fig. 2A), their relationship with 137Cs
could not be determined because of the lack of data for Na and
Ca in seawater. The leaching behaviors of Mg, Al, P, and Fe
(Fig. S2AeC) are different from those of 137Cs. These results
suggest that at least the potassium-bearing phases contained
the water-soluble and exchangeable 137Cs.
3.3. Dissolution behavior of 137Cs from as-incineratedSSAs in various reagents
Fig. 3 shows the fractions of the 137Cs and the elements dis-
solved from the Iwaki’11 sample in various reagent solutions
at 25 and 60 �C. The decrease in the percentage of 137Cs was
not proportional to the weight decrease of the ash and they
showed a sigmoidal relationship with large curvature below a
weight decrease of 50% (Fig. 3A). The greatest decrease in 137Cs
was achieved when the ash was dissolved in aqueous 6 M HCl
at 60 �C for 24 h (data labeled “K” in Fig. 3A). The decrease in137Cs was 73% and the weight decrease was 49%. The second
largest decrease in 137Cs was achieved in a saturated aqueous
oxalic acid solution at 60 �C for 24 h (data labeled “G” in
Fig. 3A). The decrease in 137Cs was 68% and the weight
Table 3 e Static leaching of 137Cs from as-incinerated SSAs, thball-milled SSAs. The leaching of 137Cs is expressed as the radiinitial radioactivity of 137Cs in the solid phase. The data shownof treatment.
Iwaki'11as-incinerated
Iwaki
Before 6 M HCltreatment
Residue after6 M HCl
treatment at60 �C for 24 h
Residue aft6 M HCl
treatment a60 �C for 24
Liquidphase
T
25 �C 60 �C 60 �C 60 �C
Pure water 0.6 ± 0.1 0.8 ± 0.3 0.24 ± 0.1 n.d
Synthetic
seawater
3.0 ± 0.1 5.6 ± 0.5 2.7 ± 0.4 5.2 ± 1.2
n.d ¼ 137Cs was not detectable in leachate.a The sample was treated by HCl twice.
decrease was 31%. The third greatest decrease in 137Cs was
obtained in a concentrated aqueous (12M) HCl at 60 �C for 24 h
(data labeled “J” in Fig. 3A). The decrease in 137Cs was 66% and
the weight decrease was 48%. The residues after exposure to
aqueous 6 M HCl, concentrated HCl, and concentrated HF at
60 �C for 24 hwere gray, indicating thatmost of the iron oxides
were dissolved, whereas the colors of the other residues were
pale brown or similar to that of the original ash.
Of the major component elements in the Iwaki’11 sample,
the relationship between the decrease in Fe and the weight
decrease (Fig. 3B) was sigmoidal with a large curvature, and
the relationship between the decrease in Al and the weight
(Fig. 3C) had a sigmoidal relationship with a small curvature.
The sigmoid curves of Fe and 137Cs were very similar. The
dissolution behavior of the other elements (P, Mg, Ca, and Si)
had no correlation with that of 137Cs (Figs. 3B, C, D). These
results strongly suggest thatmost of the HCl-soluble 137Cs was
retained by Fe-bearing phases (probably iron oxides). A weak
correlation can be seen between the dissolution behaviors of
Al and 137Cs (Fig. 3D), indicating that a small proportion of the
Al-bearing phases contained 137Cs. The Al-bearing phases that
contain 137Cs may be present in iron oxides.
eir HCl-treatment residues, and HCl-treatment residues ofoactivity percentage of the leached 137Cs with respect to theare the average values of duplicate experiments for 28 days
'11 ball-milledfor 8 h
Teganuma'11as-incinerated
Teganuma'11ball-milled for 8 h
er
th
Residue after6 M HCl
treatment at95 �C for 24 ha
Before6 M HCl
treatment
Residue after6 M HCl treatmentat 60 �C for 24 h
emperature
60 �C 25 �C 60 �C
n.d 2.2 ± 0.3 n.d
n.d 3.3 ± 0.6 6.7 ± 1.7
Fig. 3 e Dissolution of 137Cs and major component elements in the Iwaki’11 sample in various reagent solutions as a
function of the weight decrease of the SSA. The decrease of 137Cs was defined as the radioactivity percentage of the
dissolved 137Cs with respect to the initial radioactivity of 137Cs in the sample. The decrease of a given element was defined
as the weight percentage of the dissolved element with respect to the initial weight of the sample. Concentration of 137Cs
and those of the major component elements dissolved in reagent solutions were separately determined in separate
experiments.
wat e r r e s e a r c h 6 8 ( 2 0 1 5 ) 6 1 6e6 2 6 621
Similar results were obtained for the Nakakuji’12 sample
and the dissolution of 137Cs was only related to the dissolution
of Fe (Fig. S3). We did not examine the dissolution behavior of
the Iwaki’12, Teganuma’11, and Teganuma’12 samples in
detail. Similar percentages of the 137Cs (71e78%) were dis-
solved from these three SSAs by 6MHCl treatment at 60 �C for
24 h.
3.4. Characteristics of residues after HCl treatment at60 �C for 24 h
The Iwaki’11 and Teganuma’11 samples had initial radioac-
tivity concentrations of 137Cs greater than the radioactivity
criterion (8 kBq/kg). In the Iwaki’11 and Teganuma’11 sam-
ples, about 73% and 72% of the 137Cs was dissolved, respec-
tively, by 6 M HCl treatment at 60 �C for 24 h. The 137Cs
radioactivity concentrations in the HCl treatment residues
were 15 kBq/kg for the Iwaki’11 sample and 8.6 kBq/kg for the
Teganuma’11 sample (Table 4). Therefore, HCl treatment did
not reduce the 137Cs radioactivity concentrations to less than
the radioactivity criterion. The decrease in 137Cs from HCl
treatment at 95 �C for 24 h (Iwaki’11, 72%; Teganuma’11, 78%)
was similar to that from the HCl treatment at 60 �C for 24 h.
After HCl treatment of the Iwaki’11 sample, the solid res-
idue was washed with pure water 5 times and dried to
investigate the static leaching behavior of 137Cs. After 28 days
at 60 �C, 0.2% and 3% of 137Cs in the residue were leached into
pure water and synthetic seawater, respectively (Table 3).
These values are less than those of the as-incinerated (orig-
inal) Iwaki’11 sample, although water-soluble and exchange-
able 137Cs still remained in the residue.
The residues of the Iwaki’11 and Teganuma’11 samples
still contained a small amount of Fe (Table 2). The mineral
phases of the residues were silicates. Faint XRD diffraction
peaks of iron oxides were observed in a few residues. Fig. 4
shows the SEM images of the Iwaki’11 sample before (4A)
and after the HCl treatment (4B). Although most of the iron
minerals and phosphate minerals were dissolved, the mor-
phologies of the particles were not changed greatly by the
treatment.
As-incinerated SSAs consisted of two main types particles
(Fig. S4A and B). The first type of particle had a smooth surface.
Most of these particles were quartz and the rest were feldspar.
Fine particles containing Al, P, S, or Fe were attached to these
silicates. The second type of particle was dense aggregates of
numerous fine particles (typical particles are indicated with
white arrows in Fig. S4A and B). These aggregates mainly
contained Si, Al, and P. The residues after the HCl-treatment
mostly consisted of Si (Table 2). The HCl-treatment residues
were composed of three main types of particles (Fig. S4C and
Table 4 e Decrease of 137Cs in as-incinerated and ball-milled SSAs. The Nakakuji’12 sample was treatedwith concentratedaqueous HCl and the others were treated with aqueous 6 M HCl.
SSA Condition beforeHCl treatment
Decrease of 137Csby HCl treatment at60 �C for 24 h (%)
Radioactivity concentrationof 137Cs in residue treated withHCl at 60 �C for 24 h (kBq/kg)
Decrease of 137Cs byHCl treatment at 95 �C
for 24 h (%)
Iwaki'11 As-incinerated 73 ± 1 14.8 ± 0.3 72 ± 1
Ball-milled 8h 85 ± 0 5.9 ± 0.1 90 ± 1
Iwaki'12 As-incinerated 78 ± 1 e e
Ball-milled 8h 85 ± 0 2.0 ± 0.1 90 ± 0
Teganuma'11 As-incinerated 72 ± 1 8.6 ± 0.1 78 ± 0
Ball-milled 8h 85 ± 0 4.1 ± 0.1 88 ± 0
Teganumai'12 As-incinerated 71 ± 1 e e
Ball-milled 8h 87 ± 0 1.9 ± 0.1 90 ± 0
Nakakuji'12 As-incinerated 71 ± 0 e 79 ± 0
Ball-milled 8h 73 ± 0 0.9 ± 0.0 83 ± 0
wat e r r e s e a r c h 6 8 ( 2 0 1 5 ) 6 1 6e6 2 6622
D). The first type was quartz and feldspar particles with a
smooth surface. The second type was fibrous particles (typical
particles are indicated with a blue arrow in Fig. S4C). The third
type was particles that appear to be sparse aggregates of fine
particles (typical aggregates are indicated with red arrows in
Fig. S4D). The second and the third type of particles are
probably the silicate framework of the dense aggregates that
retain fine particles of phosphates and iron oxides. Some of
the third type of particles contained a small amount of Fe. In
addition, there was a further type of particles that contained
high concentrations of Fe. An example of one of such particle
is shown in Fig. 4C (particle 1). This particle appeared to be a
dense aggregate of numerous nano particles and had a high Fe
content of 8% byweight (Si 60% andAl 20%). Fewas detected in
the whole particle. The other particles in Fig. 4C contained
almost no Fe; Fe was not detected in small particle 2 that had
morphology similar to particle 1. These results suggest that
the internal Fe in the large aggregate was not dissolved
because the hydronium ions did not penetrate the particles. It
was predicted that pulverizing these aggregates would
enhance dissolution of radioactive Cs.
3.5. Effect of pulverization
To examine the effect of pulverization, preliminary experi-
ments were conducted using three pulverized powders from
the Iwaki’11 sample prepared by dry pulverization with an
automatic agate mortar for 1, 4, and 10 h, respectively. The
Fig. 4 e SEM images of (A) the as-incinerated Iwaki’11 sample an
The large particles with smooth surfaces were mainly quartz.
grain sizes of the pulverized samples decreased with
increasing pulverization time. However, the grain sizes were
not uniform and small aggregates were still present in the
sample pulverized for 10 h (Figure S5 in Supplementary
content). When these samples were immersed in aqueous
6 M HCl at 60 �C for 24 h, a larger amount of 137Cs was dis-
solved as the particle sizes decreased (Figure S6 in
Supplementary content). This demonstrates that pulverizing
SSA is a promising pretreatment method for effectively dis-
solving 137Cs.
Because the mortar pulverization did not produce an SSA
sample with a uniform grain size, wet pulverization with a
planetary ball mill was used to prepare homogeneous ultra-
fine powers. This method has another advantage; a larger
amount of material can be pulverized at once. Ball milling for
more than 4 h produced particles less than 1 mm in size with
uniform grain sizes, and no large aggregates (Figure S5D). No
further size reduction was achieved by ball milling for up to
24 h. The following experiments used SSA samples ball-milled
for 8 h.
The ball-milled SSA samples were treated with aqueous
HCl at 60 �C for 24 h. The ball-milled Nakakuji’12 sample was
treated with concentrated HCl and the other ball-milled SSAs
were treated with aqueous 6 M HCl. Greater amounts of 137Cs
were dissolved from the ball-milled samples than from the as-
incinerated (not pulverized) samples (Table 4). The radioac-
tivity concentrations of 137Cs in the HCl-treatment residues of
the ball-milled Iwaki’11 and Teganuma’11 samples were
d (B, C) its residue after 6 M HCl treatment at 60 �C for 24 h.
Table 5 e Elemental compositions of HCl-treatment residues determined by XRF.
Residues ofIwaki'11
Residues ofTeganuma'11
Residues ofNakakuji'12
Residues ofIwaki'12
Residues ofTeganuma'12
Ball-milled8 h
Ball-milled8 h
Ball-milled8 h
As-incinerated Ball-milled8 h
Ball-milled8 h
Ball-milled8 h
Ball-milled8 h
Ball-milled8 h
Ball-milled8 h
6 M HCl,60 �C, 24 h
6 M HCl,95 �C, 24 h
6 M HCl,95 �C,
24 h, twice
6 M HCl,95 �C,24 h
6 M HCl,60 �C,24 h
6 M HCl,95 �C,24 h
Conc. HCl,60 �C,24 h
Conc. HCl,95 �C,24 h
6 M HCl,95 �C, 24 h
6 M HCl,95 �C, 24 h
SiO2 88.0 91.6 94.1 82.6 90.2 92.3 88.8 91.1 91.6 92.3
Al2O3 4.8 3.1 2.4 7.7 3.4 2.3 4.3 3.6 2.8 2.3
P2O5 2.0 2.2 1.4 0.4 2.2 2.4 1.8 1.8 2.6 2.5
MgO 0.2 0.1 0.1 0.8 0.2 0.2 0.2 0.2 0.1 0.1
CaO 0.6 0.4 0.4 2.1 0.3 0.3 0.6 0.4 0.3 0.2
Fe2O3 0.9 0.4 0.2 2.1 0.7 0.4 0.7 0.3 0.4 0.3
Na2O 0.5 0.5 0.0 0.7 0.0 0.2 0.4 0.6 0.0 0.0
K2O 1.3 0.6 0.3 1.9 1.2 0.5 1.5 1.0 0.5 0.6
TiO2 1.2 0.9 0.8 1.2 1.7 1.3 1.3 0.9 1.5 1.4
NiO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
CuO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
MnO 0.0 0.0 0.0 0.1 0.0 0.0 0.0 0.0 0.0 0.0
ZnO 0.2 0.1 0.0 0.2 0.0 0.0 0.0 0.0 0.0 0.0
SrO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
ZrO2a 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
BaO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
PbO 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
As2O3 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
SO3 0.1 0.0 0.0 0.1 0.0 0.0 0.0 0.0 0.0 0.0
Cl 0.2 0.1 0.1 0.1 0.1 0.1 0.2 0.1 0.1 0.1
Total
weight %
100.0 100.0 100.0 100.0 100.0 100.0 100.0 100.0 100.0 100.0
a Ball-milled SSAs contained 1% Zr in terms of ZrO2. Because as-incinerated SSAs contained no Zr (Table 2), elemental compositions of HCl-treatment residues were recalculated by setting ZrO2 to
zero.
water
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wat e r r e s e a r c h 6 8 ( 2 0 1 5 ) 6 1 6e6 2 6624
reduced to less than the radioactivity criterion (8 kBq/kg).
From the ball-milled Iwaki’11 sample, slightly larger amounts
of Fe and Si (Fe 6.3%, Si 0.9%, weight percent of the dissolved
weight of the element with respect to the initial amount of
SSA) were dissolved than from the as-incinerated sample (Fe
6.0%, Si 0.3%). This result suggests that some of the 137Cs was
dissolved from the silicates, probably because of the increased
surface area created by pulverization.
The HCl-treatment residues of the ball-milled Iwaki’11 and
Teganuma’11 samples were subjected to the static leaching
test at 60 �C for 28 days. Before use, the HCl-treatment resi-
dues were washed with purified water five times, dried in air
at 60 �C, and lightly ground in an agate mortar. After the static
leaching test in purified water, 137Cs was not detectable in the
leachate (Table 3). However, the 137Cs leached into the syn-
thetic seawater (5.2e6.7%) was at similar levels to the 137Cs
leached from the as-incinerated samples into the synthetic
seawater (5.6%). These results mean that a fraction of the HCl-
soluble solid phases containing 137Cs remained undissolved
after the HCl treatment. A small amount of the Fe-bearing
phases remained in the HCl-treatment residues (Table 5).
Several minutes after adding the ball-milled samples to
aqueous HCl, the powders flocculated to form millimeter-
sized aggregates. It is likely that the flocculation impeded
the penetration of HCl into the aggregates.
3.6. Dissolution of 137Cs at 95 �C
The effect of raising the temperature on the dissolution of137Cs was investigated. As shown in Table 4, the 6 M HCl
treatment at 95 �C of the as-incinerated Iwaki’11 sample did
not increase the dissolution of 137Cs. For all the ball-milled
SSA samples, more 137Cs was dissolved at 95 �C than at 60 �C.When the ball-milled Iwaki’11 sample was treated with
aqueous 6 M HCl at 95 �C twice, the second treatment only
dissolved a small amount of 137Cs (0.4%) together with Fe
(0.02%) and Si (0.2%). Two 6 M HCl treatments at 95 �Cdecreased the radioactivity concentration of 137Cs in the ball-
milled Iwaki’11 sample residue from 5.9 (60 �C) to 4.8 kBq/kg.
After the two 6MHCl treatments at 95 �C, the Fe content in the
residue of the Iwaki’11 sample decreased to 0.2% Fe2O3 (Table
5). SiO2 and Al2O3 accounted for most of the residue in the
Iwaki’11 sample (96.5% in total) (Table 5), indicating that the
residue was mostly silicates. For this residue, XRD diffraction
peaks of quartz and feldspar were observed, although no
peaks for other minerals were observed (Fig. 5). This residue
was used for the static leaching test after washing with pure
water 5 times. After 28 days in pure water and synthetic
seawater at 60 �C, 137Cs was not detected in the leachates
(Table 3). This result demonstrates that the 137Cs in the res-
idue is strongly immobilized in the silicates.
Fig. 5 e XRD patterns of residues of ball-milled SSAs after
heating in aqueous HCl at 95 �C for 24 h. The ball-milled
Iwaki’11 and Teganuma’11 samples were heated in
aqueous 6 M HCl, and the Nakakuji’12 sample was heated
in concentrated aqueous HCl.
4. Discussion
Although there is no data available on the chemical states of137Cs in raw sewage sludge, the 137Cs was assumed to be
adsorbed on sewage sludge components, such as organic
substances and minerals. When dehydrated sewage sludge is
incinerated, organic compounds are decomposed and new
minerals form. The 137Cs in organic substances is thought to
have been redistributed to pre-existing and newly formed
mineral phases. Therefore, it is not possible to compare the
chemical states of 137Cs in SSA with those in other contami-
nants, such as contaminated soils.
We revealed that most of the 137Cs in SSAwas contained in
Fe-bearing phases, such as iron oxides (e.g. hematite), and
some of the 137Cs was strongly immobilized in silicates, such
as quartz, feldspar, and talc. However, iron oxides, quartz, and
feldspar have very low sorption capacities for Cs (Torstenfelt
et al., 1982; Akiba et al., 1989; Sasaki et al., 2007; Bellenger
wat e r r e s e a r c h 6 8 ( 2 0 1 5 ) 6 1 6e6 2 6 625
et al., 2008; Giannakopoulou et al., 2012; Ohnuki et al., 2013).
The sorption of Cs on talc is unknown. Talc (Mg3Si4O10(OH)2) is
a 2:1 clay mineral. Although its structure is similar to that of
mica, the sorption capacity of talc for Cs is thought to be very
low because talc has no negative charge in the structure. A
fraction of talc in the HCl treatment residues of the ball-milled
SSAs was probably lost, because planetary ball milling for 6 h
converts the structure of talc to an amorphous structure and
the Mg is leached by heating in aqueous HCl at 80 �C (Yang
et al., 2006). In fact, the XRD diffraction peak at 9.4�e9.5�
observed for as-incinerated SSAs was not observed for resi-
dues of the ball-milled SSAs after heating in aqueous HCl at
95 �C for 24 h (Fig. 5). Therefore, minerals with very low
sorption capacities retained 137Cs in SSAs.
There are two possible mechanisms for the retention of137Cs. The first is containment in aggregates, where dense
aggregates composed of fine mineral particles sorbing 137Cs
physically confined the 137Cs. The second is strong bonding
that becomes significant at extremely low Cs concentrations.
The sorption behavior of Cs on minerals depends on its
concentration; as the concentration of Cs decreases, the
fraction of the Cs tightly sorbed on minerals increases
(Ohnuki et al., 2013). This could be because many minerals
have strong affinity sites for Cs at very low site densities. In
the ball-milled Iwaki’11 sample, which had the highest con-
centration of 137Cs, the mole concentrations of 137Cs in the
iron oxides and the silicates are estimated to be 3 � 10�10 and
1 � 10�11 mol/kg, respectively. These concentrations are
extremely low. We should also consider the possibility that
when the iron oxides and silicates were heated during the
incineration of the sewage sludge, the sorbed 137Cs diffused
inside their crystals and this made it more difficult to desorb
the 137Cs.
Dissolution of 137Cs from SSAs was increased by heating at
95 �C. Kawamoto et al. developed a method for effectively
dissolving 137Cs from contaminated Fukushima soils by
heating in aqueous 0.5 M HNO3 at 95 �C (Kawamoto et al.,
2013). We tested dissolution behavior of the ball-milled
Iwaki’11, Teganuma’11, and Nakakuji’12 samples in aqueous
0.5 M HNO3 at 95 �C. For the ball-milled Iwaki’11 and Tega-
numa’11 samples, the decrease in 137Cs caused by aqueous
0.5MHNO3 treatmentwas similar to that achieved by aqueous
6 MHCl (Table S1). For the ball-milled Nakakuji’12 sample, the
decrease in 137Cs caused by aqueous 0.5 M HNO3 was
approximately 8% greater than that caused by concentrated
aqueous HCl. The residues after the 0.5 M HNO3 treatment
were brown, showing that a large amount of iron remained
undissolved. The decrease in Al and P caused by aqueous 0.5M
HNO3 treatment was similar to that caused by aqueous 6 M
HCl. A considerable amount of Si was dissolved by a aqueous
0.5 M HNO3, whereas Si was hardly dissolved in aqueous 6 M
HCl. The decrease in Fe by aqueous 0.5 M HNO3 was less than
that by aqueous 6 M HCl (Table S1). As shown in Table 5, the
content of Fe in the residue treated with aqueous 6 M HCl at
95 �C was very low. These results indicate that for the 0.5 M
HNO3 treatment, some of the 137Cs in the iron oxides remained
undissolved and some of the 137Cs in silicates were dissolved
together with Si. As discussed previously, the 137Cs in silicates
is non-leachable and that in HCl-soluble phases, including
iron oxides, is leachable. To develop SSA treatment methods,
it is necessary to consider the amounts of 137Cs and the min-
eral phases that dissolve.
5. Conclusions
We investigated the characteristics of 137Cs in radioactively
contaminated SSAs produced after the Fukushima Daiichi
nuclear accident. We can draw the following conclusions.
Most of the 137Cs in SSAs was contained in Fe-bearing
phases, which were probably iron oxides, and a minor frac-
tion of the 137Cs was contained in silicates. A tiny amount of
the 137Cs was contained in K-bearing phases, which were
probably alkali metal salts. There was no evidence to show
that the 137Cs was contained in the major mineral phases,
which were phosphates. At least some of the 137Cs in the Fe-
bearing phases and K-bearing phases were leachable to
environmental water.
Heating SSAs in aqueous HCl dissolved a large fraction of
Fe-bearing phases and the radioactivity concentration
decreased. However, in SSAs, there were many aggregates of
nanosize particles of Fe-bearing phases and silicates, and the
Fe in these aggregates was not easily dissolved in aqueous
HCl. Because of this, the radioactivity concentrations of 137Cs
in the SSAs did not decrease below the radioactivity criterion
for landfill disposal in Japan. Pulverization of SSAs was the
most effective pretreatment for dissolving Fe-bearing phases
in aqueous HCl in the following two respects. The method
reduces the radioactivity concentrations of 137Cs in SSAs
below the radioactivity criterion. The 137Cs was very strongly
immobilized on the HCl-treatment residues, which were
mostly silicates. Thus, 137Cs should not leach to environ-
mental water from these residues.
Appendix A. Supplementary data
Supplementary data related to this article can be found at
http://dx.doi.org/10.1016/j.watres.2014.10.038.
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