J. Aerosol Sci., Vol. 18. No. 6, pp. 931-934, 1987.
0021-8502/87 $3.00+0.00 Pergamon Journals Ltd.
Printed in Great Britain
DETAILED CHEMICAL ANALYSIS OF AEROSOLSCARRYINGRADIOACTIVITY AND COLLECTED WITH MICA TRACKMICROFILTERS P. Vater, R. Dersch, R. Brandt Kernchemie, FB 14, Philipps-Universit~t, Marburg G. Luthardt, W. Rudolph NUKEMGmbH, Hanau
Introduction Measurements of aerosols carrying radioactivity within an industrial plant producing nuclear reactor fuel elements have to be done to ensure the workers' safety and to make certain that the exposure does not exceed permissible limits. The environmental air near such a working place contains conventional dust particles and a few radioactive particles which consist mostly of uranium compounds having an isotopic composition like the uranium actually used in the fabrication process for nuclear reactor fuel elements. The incorporation of these particles above the permissible limit could endanger the health and has therefore to be carefully controlled. The deposition of aerosols in the lung depends mainly on their particle size, the retention therein on their chemical and physical properties. These qualities must be known for preventive measures to ensure the workers' radiation protection. Knowing these qualities one should be able to infer from the measured activity of aerosol particles in the environmental air the value for the incorporated activity. To study some global properties of aerosols there exist several established methods, but there is composition of individual
a lack of
information concerning the
chemical
aerosol particles and of the size distribution of particles
having a certain chemical composition. We apply a Mica Microfilter Cascade Fractionator (MMCF) to collect aerosol particles from the environmental air near a working place at an industrial plant producing nuclear reactor fuel elements. By using Scanning Electron Microscope (SEM) and Energy Dispersive X-ray Analysis (EDXA) the individual
particles
can be investigated.
Experiment Figure l shows a photograph of the Mica Microfilter Cascade Fractionator (MMCF), and a sketch of the air inlet section. The MMCF contains three or four mica f i l t e r s having different pore sizes which decrease from about lO ~m at the air inlet side down to about l ~m for the last f i l t e r . At the end, a glass fiber f i l t e r acts as an
931
932
P. VATER et aL
absolute f i l t e r .
The outer diameter of the
mm, the diameter of the f i l t e r i n g porosity is
filters
is 50
area 40 mm. The f i l t e r
about 5 %. The use of supporting
grids
and
relatively low pressure differences (up to about 0.25 bar) guarantee for
the mechanical
stability
of
the
filters
during the experiment. By using a bypass the air throughput is controlled to be about lO0 I/h, the total throughput is a few m3. After the aerosol sampling the mass load of the f i l t e r s is determined by weighing and the collected alpha-activity is measured with
a methane flow counter.
After
scanning electron
microscope (SEM) with
attached
dispersive
X-ray
investigate the ~
analysis
system (EDXA) is
that,
a
energy
used
particles collected at the f i l t e r s .
to
Thus,
Roof
the
Cone
chemical composition
(assuming a spherical determined.
In
this
and
the
geometrical
diameter
shape) of individual particles can be way particle
size
distributions
of
uranium and conventional dust particles can be obtained. The Mi¢o Filter Supporting Grid
- I b m --dldB
50 mm
median particle size is characterised by the 50 %-value of the frequency distribution of the particle sizes. As an example, figure 2 shows SEM photographs of(right) an
Figure l:
uranium and ( l e f t )
The MMCFand i t s
a steel-particle together with the
respective X-ray spectra.
air i n l e t section. 1 03 3
I04 i
1
3
Figure 2:
S
2
9
II
13
2
4
6
8
I0
12
14
IG
K.U
SEM photographs of (right) an uranium and ( l e f t ) a steel particle together with the respective X-ray spectra.
Results and Discussion During the last years different experiments at different times have been carried out in the same factory I-3.
The results
given in this
paper are,
to some extent,
preliminary and averaged. The specific mass load and specific a c t i v i t y of air were found to be in the order of (0. I-0.4) mg/m3 and (0.15-0.3) Bq/m3, respectively. Both values are
in
good agreement with
results
of
independent measurements using
different
techniques. As a typical example of measured mass load and alpha-activity of individual f i l t e r s , the results of the last experiment are quoted in the following table.
Chemical analysis of aerosols carrying radioactivity
filter
pore sizes
mass l o a d
(~m)
(mg)
933
alpha-activity (Bq)
l
9.2
0.2
(0.63 + O.Ol)
2
4.4
O.l
(O.ll + O.Ol)
3
1.3
0.3
(0.033+ 0.006)
m
4
glass fiber
not measurable
not measurable
More than three fourth of the activity was found on the f i r s t f i l t e r
which is loaded
only by one third of the total mass load. This indicates that most of the collected mass consists of conventional
dust particles
and the mean size of uranium particles
is
expected to be larger than that of conventional dust particles. This can be seen in figure
3 where the
particle
size distributions
of
uranium and conventional dust
particles collected at the same f i l t e r (in a previous experiment) are plotted. The geometrical particle sizes are characterized by the "median" C, where uranium (C=2.0 Nm) exhibits a significant larger diameter than conventional dust (C=0.35 Nm) particles.
/
Jl:
Figure 3: Frequency distributions
of
geometrical particle sizes of
.
(left)
uranium and
(right)
conventional dust particles.
°°f
U- Particles
4' U - Porticies
C , 2.0 wn
o:s ,:o ;
~
~:lrt~cle S~ZS[iJm)
;o
C - 0.3S pm
~'o.s Z,
~
~ r t l c ( e size (pro)
;o
In the last experiment we found a comparable result of C=l.9 Nm for
uranium
particles. In this experiment we have investigated all particles ~O.2Nm in a certain well defined f i l t e r area. From the number of uranium particles found on this area (29), the median value of the geometrical size (C=l.9 Nm), the isotopic composition of uranium actually used in the fabrication process during the experiment, the total
filter
area
and the assumption that the uranium particles consist of UO2 and are of spherical shape, the total alpha activity of the loaded f i l t e r can be calculated to be (0.52+0.31) Bq. This result is in rather good agreement with the actual measured value of (0.63+0.01) Bq (see Table) indicating that the examined fraction is indeed representativ of the total f i l t e r area. Conclusion The MMCFtogether with the evaluation using SEM/EDXA is proved to be a useful tool to determine the size distribution
of aerosol particles
having a certain
chemical
composition, e.g. of uranium particles. Investigations of uranium particle sizes collected from the environmental air
at an
industrial plant show a rather large value for the median geometrical particle size. Taking into account the large specific gravity of UO2, the AMAD-value (activity median
934
P. VATER et al.
aerodynamic diameter) should be correspondingly large. Respective calculations are in progress to convert geometrical sizes into aerodynamical ones. Acknowledgements We are indebded to Drs. R. Spohr and J. Vetter for kindly arranging the mica irradiations
at
the
UNILAC (GSI, Darmstadt). This
work was
Bundesminister fur Umwelt, Naturschutz und Reaktorsicherheit
supported
by
the
(Bonn).
References Dersch, R., et al.
(1985) "Health Protection
Investigations at a Working Place Using a
Mica Microfilter Cascade Fractionator (MMCF)", GSI 85-I (Scientific Report 1984) 264 Dersch, R., et al. (1986) "Chemical Analysis and Size Distribution of Aerosols Collected with Mica Track Microfilters", GSl 86-I (Scientific Report 1985) 266 Vater, P., et al. Tracks 12, 981
(1986) "Industrial Applications of Mica Track Microfilters", Nuclear