diffusion from a ground level point source experiment with ... · rotameter of max. capacity 400...
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AE-353 UOC 539.1.073.5
614.7 621.039.85
Diffusion from a Ground Level Point Source
Experiment with Thermoluminescence
Dosimeters and Kr 85 as Tracer Substance.
Ch. Gyllander, S. Holiman and U. Wsdemo
AKTIEBOLAGET ATOMENERGI
STOCKHOLM, SWEDEN 1969
AE-353
DIFFUSION FROM A GROUND LEVEL POINT SOURCE
Exper iment with thermoluminescence dos imete r s and Kr 85 as t r a c e r
substance
Ch Gyllander, S Hollman and U Widemo
ABSTRACT
Within the f ramework of the IRIS-project (Iodine R e s e a r c h
in Safety Projec t ) an exper iment to study diffusion at nea r -g round
level was c a r r i e d out on 19 December 1967 using Kr as the
t r a c e r e lement . The object of the exper iment was
a) to t es t the method using |3-sensitive thermoluminescence
dos ime te r s under actual field conditions.
b) to study the init ial dilution from a ground level point sou rce .
The t e s t a r e a chosen was the Tranvik valley just south of
Trobbofjärden, an inland bay of the Bal t ic . Dose dis tr ibut ions have
been studied at two sec t ions , 50 and 200 m respec t ive ly , from the
r e l ea se point.
At each level var ious d i spers ion p a r a m e t e r s have been ex
per imenta l ly determined and thei r conformity to normal dis tr ibut ion
have been calculated. Dilution factors valid for the centre of the plume
a r e re la ted to the values repor ted in the l i t e r a t u r e .
The exper iment was made under ideal weather conditions
above snow-free ground. Resul ts of the next exper iment , a point
r e l e a s e at ground level from a building at Studsvik, a r e expected
to yield valuable information concerning the effect of buildings on
the diffusion pa t te rn .
Pr in ted and dis t r ibuted in Apri l 1969.
CONTENTS Page
PLANNING OF THE EXPERIMENT 3
1. 1 General 3
1.2 Objective 3
EXPERIMENTAL METHOD 4
2. 1 Test a r ea 4
2.2 Dosimeter sections 4
RELEASE EQUIPMENT 6
RADIOLOGICAL DATA 6
4. 1 T r a c e r element 6
4 .2 Dos imeters 7
METEOROLOGICAL DATA 8
RESULTS 9
6.1 Background 9
6. 2 Dose distr ibution 9
6. 3 Total quantity of activity 10
6.4 The diffusion p a r a m e t e r s a and <j 10 r y z
6..5 P lume width 16 -2
6. 6 Relative concentrat ion, m 16
RADIATION PROTECTION 18
7. 1 Control of safety analysis 18
7 .2 Relationship between source s t rength - sampling
t ime - dose 18
CONCLUSION 19
REFERENCES
- 3 -
1. PLANNING OF THE EXPERIMENT
1. 1 General
A great deal of exper imenta l data is available for chimney-
r e l e a s e s . This m a t e r i a l was obtained from meteorologica l inves t i
gations in Studsvik and Ågesta from I960 to 1963. Concerning dif
fusion in near -g round layers s imi la r exper imenta l m a t e r i a l is not
available for Swedish conditions.
The method using thermoluminescence dos ime te r s to m e a s
u re an active t r a c e r substance (Bjärngard 1963, 1964) has been t r i ed
in init ial exper iments at Studsvik, both for r e l ease over ice and over 41 level ground using A , which emits both Y-photons and |3-par t ic les .
When a Y~emitting t r a c e r is used the dose distr ibution d e
pa r t s s trongly from the concentrat ion distr ibution since the dos i
m e t e r rece ives radiat ion from a re la t ively large volume. As a r e
su l t of this cer ta in theore t ica l difficulties assoc ia ted with evaluations
occur .
F o r (3-part icles, however, the range in a i r is very l imited.
By using pure (3-emitters as t r a c e r s and p-sens i t ive dos imete r s the
concentrat ion dis tr ibut ion can be studied more d i rec t ly .
1. 2 Objective
Within the f ramework of the IRIS-project an exper iment to
study diffusion at nea r -g round level was ca r r i ed out at Studsvik in 85
Dec. 1967 using Kr as the t r a c e r e lement . The object of the exper iment was :
a) to tes t the method using (3-sensitive dos ime te r s under actual
field conditions,
and
b) to study the init ial dilution from a ground level point source .
Ideal r e l ea se conditions, which r a r e l y prevai l in p rac t i ce ,
were chosen for this f i rs t exper iment . It has been considered d e
s i rab le to s t a r t the s e r i e s of exper iments by measur ing within as
well-defined an environment as poss ib le , so that a compar ison
can be made with theore t ica l calculations and with the resu l t s of
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diffusion exper iments e l sewhere , and with other methods , e .g .
P r a i r e G r a s s , Green Glow, e tc . in the USA. At a la ter date a com
par i son will a lso be possible between resu l t s of point r e l e a s e s in an
open field and r e l ea se s from buildings.
2. EXPERIMENTAL METHOD
2. 1 Test a r ea
The tes t a r e a chosen was just south of Trobbofjärden, an in
land bay of the Bal t ic , in the Tranvik valley where exper iments could
be ca r r i ed out for north or south winds. This a r e a is indicated on the
map (scale 1:50 000) on page 5. For a north wind the nea re s t farm is
Tranvik, 1300 m from the r e l ea se point.
A safety analysis showed that the diffusion 1 km from the r e
lease point would give r i s e to a concentration which, under neut ra l
weather conditions and a wind speed of 5 m / s e c . , would be lower
than that allowed for continuous exposure ( yrr M P C , , g ) i. e. the
concentrat ion pe rmis s ib l e for population groups in the vicinity of
a nuclear plant .
F o r a south wind the distance to the nea re s t habitation north
of Trobbofjärden exceeds 3 km.
Wind direct ions during the exper iments were as indicated
on the map
in the Tranvik valley at the 10 m. level , 315
at the main meteorologica l tower at the 36 m . level , 305 .
Thus the wind was blowing towards the Studsvik a r e a .
2 .2 Dosimeter sections
F o r determinat ion of the initial dilution two sections were
laid out (parts of c i rcu lar a rc s ) at dis tances of 50 m and 200 m r e
spectively from the r e l ea se point. The intention was that the 50 m
section should give a detailed pic ture of the dose within the zone
where l a rge concentrat ion gradients st i l l occur , whilst the section
at 200 m should reflect the conditions within the centra l p a r t of the
plume only so that the maximum value of the concentration at this
distance could be de termined unambiguously.
A '."rCk-S\ - .•' -UHM?///- - V ~.Ji -re ^sztskvr^rn. •• \w/j
^ " " v « THE STUDSVIK AREA
^ B 5 ^ m M f i > ^ « w l l Wind direction during diffusion experiment fe
mm^i^ms^m^^^^ j n t h e T r a n v i k v a l t e y 19J2.1967 • *
Scale 1:50000 t
For spridning godkänd i Rikels allmänna kartverk den 12 ,' 12 1968 SVENSKA REPRODUKTIONS AB, Stockholm 1969 543 - 92325
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Table 1 Dosimeter sections
Section
50 m
200 m
Width
50 m
100 m
Angle
1 radian
0 .5 radian
Distance between ver t i ca l s
2 .5 m
10 m
Dosimeter levels
0 , 2 , 4 , 6 , 8 m
0 , 4 , 8 , m
Nos of ver t ica l s
19
11
Nos of dos i m e t e r s
95
33
19 dos ime te r s dis t r ibuted on the various levels were used for measur ing
the background.
Before the s t a r t of the experiment cer ta in minor changes were
made of the dos imete r sect ions in order to adjust them for the actual
wind di rect ion. The final a r r angement is apparent from the dose pa t te rn
shown on page 10.
3. RELEASE EQUIPMENT
The a r r angemen t used for r e lease of the t r a c e r gas compr ised
the following. A reducing valve and thrott l ing valve were connected to
a gas tube. The gas flow ra te leaving the gas tube was m e a s u r e d by a
ro t ame te r of max. capacity 400 l i t r e / m i n , whilst the total volume of
gas r e l eased was m e a s u r e d by a ga sme te r .
Gas was r e l eased through an a r r angemen t consist ing of a
conical funnel of 11.5 cm rad ius . This funnel was covered by a p e r
forated p las t ic film. The ra te of flow of gas through the holes has been
calculated to be ca 3 m / s e c .
It was intended to locate the r e l ease point as near ground as
poss ib le . Due to the roughness of the ground together with a slight
uphill slope in the d i rec t ion of flow the r e l ea se point was placed 1 m
above ground level in o rder to obviate the r i sk of ground contact in
the immedia te vicinity which would give r i s e to a continued i r r egu l a r
flow.
4. RADIOLOGICAL DATA
4. 1 T r a c e r element
Kr is an a lmost pure (3-emitter which emits 0. 67 MeV
(max. energy) (3 par t ic les in 99. 6 % of the d i s in tegra t ions . Its half-
life is 10 y e a r s . The range in a i r is 1.75 m which implies that a
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spher ica l cloud of 3. 5 m d iameter gives to a dos imeter at the cloud
centre a dose which is identical with the dose from a cloud of infinite
extent.
B-I Rudén (1965) has calculated, with reference to Hine &
Brownell , that a cloud 1. 5 m in d iameter gives 97 % of the dose from
an infinite cloud. For p rac t ica l purposes the dose dis t r ibut ion can
therefore be considered to coincide approximately with the concent ra
tion dis t r ibut ion. 85 Kr , in containers each holding 25 Ci, has been purchased
from Oak Ridge National Labora tory , USA. The volume of each con
ta iner was 300 ml , the p r e s s u r e inside was 760 m m Hg, and the space
between the container and the t r anspo r t shield was filled with lead
shot. Fo r the diffusion exper iment a g rea t e r volume was requ i red
and thus the active gas was t r a n s f e r r e d to a 40 l i t re compressed
a i r tube. The filling was c a r r i e d out at the Isotope Cent re . I m m e
diately before the exper iment the tube was filled with a i r , and a f t e r
wards t r a n s f e r r e d to the tes t a r e a .
Exper imenta l data: Q C
Amount of Kr r e l eased 24. 1 Ci ± 5 %
Exposure t ime 52 min
Background, average for 19 dos ime te r s 108 jj R
4. 2 Dos imete rs
The dos imete r s a r e of type AE-CaSO,:Mn with myla r film 2
lids (1 m g / c m ). B-I Rudén (1965) has ca r r i ed out a fair ly large Q C
number of cal ibrat ion exper iments with Kr . F r o m these expe r i -85 ments the TLD constant for Kr was found to be
0.01 £ i . hr m R
i. e. 0. 01 x the exposure ( =—) = concentration ( ^ , ). m
- 8 -
5. METEOROLOGICAL DATA
The following measu remen t s have been made par t ly within
the exper imenta l a r e a , and pa r t ly at the main meteorologica l tower
at Studsvik.
Table 2 Meteorological data
Measurement
Within the e x p e r i
menta l a r ea
Wind speed
Wind direct ion
Wind speed
Tempera tu re
At the main m e t e o r o
logical tower
Wind speed
Wind speed
Wind di rec t ion
Wind direct ion
Tempera tu re difference
Type of ins t rument
Lambrecht , r e co rd .
AE Special ,
Fues s
The rmis to r br idge , manually fed.
Lambrech t , r e c .
Lambrech t , "
AE Special , "
AE Special , "
The rmis to r br idge , "
Height, m e t r e s
10
10
1.5
0.2 2 5
10
36
72
36
72
30-2
Meteorological data prevail ing during the ex per iment
2. 5 m / s e c
310° - 320°
1. 1 m / s e c
-9 . 5 - -8 .8°C - 9 . 7 - -8 .9°C -9 .7 - -9 .0°C - 9 . 7 - -9 .0°C
3. 3 m / s e c
5. 8 m / s e c
300° - 310°
340° - 360°
-0 .2°C
On the bas i s of the t empera tu re difference between 2 and 30 m
and the wind speed at the 72 m level the diffusion p a r a m e t e r , A., is
found to be 0. 3.
- 9 -
X is defined as
X = 10 log ^ | — • 103
uf
where -— = vertical gradient of potential
temperature, C/100 m
u. = the wind speed above the friction layer, the so-called
"free wind", m/sec.
6. RESULTS
6. 1 Background
19 dosimeters were used for background measurements. The
average value of the background exposure, m, was determined as
follows:
- , / S(x . -x) 2 ' m = X ± t o - V n(n-l)
where x = the arithmetic mean dose
x. = the individual dose values i
n = number of dosimeters t = 2. 101 for 5 % error probability a 3
m = 108 ± 11 |iR
The scatter of the individual dose values was somewhat larger
than expected:
2 a = 44 |i,R
6. 2 Dose distribution
The dose values, after correcting for background, were plotted
in a diagram and isodose lines were drawn (diagram 1, page 11).
- 10 -
6, 3 Total quantity of activity
The total quantity of activity which passed the 50 m section
has been checked. In drawing the isolines an accurate interpolation
was made from curves showing the distribution in the vertical di
rection. The calculation was made by means of graphical integration
and was limited to that part of the measuring plane within the 100 (j,R
isoline. Dose values were subsequently transposed to concentrations.
From the wind profile near the ground an average wind speed of
1.75 m/s was determined for the 0-10 m layer. The following results
were obtained:
Quantity of activity released 24. 1 Ci ± 5 %
Quantity of activity which passed 21 Ci ~ 88 % the 50 m section
Some uncertainty is of course associated with a determination
of this kind, but the check shows that the central parts of the active
plume must have been located within the dosimeter grid during the
whole experiment. This is also confirmed by wind direction data. Due
to the method of interpolation used, the error in drawing the isolines
should be small. The greatest error probably results from the use of
an average wind speed for the 0-10 m layer. The total error associated
with the calculation of the quantity of activity which passed the section
is, however, unlikely to exceed ±10 %.
6.4 The diffusion parameters a anda £ y i±z
A formula for continuous ground level point release has been
deduced by Högström (1964) on the Studsvik-Ågesta data:
2VTT • I • o y • a z • u 3 6 2 Q y 2a z
X_ = concentration of material M at the points (x, y, z) M/m
Q ~ release rate of material M M/s
x,y, z= direction coordinates m
a = horizontal diffusion parameter m y
o- = vertical - " - - " - m _z xx = wind speed at reference level 36 m m/s
So I = a function of x obtained from the equation of continuity
Diagram 1 DIFFUSION EXPERIMENT WITH Kr 85 IN THE TRANVIK VALLEY 19.12.1967.
DOSE,yuR BACKGROUND: MEAN VALUE OF 19 DOSIMETERS 108 pR EXPOSURE TIME: 52 MIN. =0.866h.
$ • h";
o in
Z O
<o
u 111
- 12 -
In o r d e r to m a k e a q u a n t i t a t i v e e s t i m a t e of how w e l l the d i s -2
t r i b u t i o n a p p r o x i m a t e s to the n o r m a l d i s t r i b u t i o n , a X t e s t w a s m a d e
c o n c e r n i n g the diffusion p a r a m e t e r a . E a c h l e v e l w a s t r e a t e d s e p
a r a t e l y . The r e s u l t of s u c h a t e s t does no t , h o w e v e r , show w h e r e t h e
d i s c r e p a n c i e s o c c u r . Skew and e x c e s s w e r e c a l c u l a t e d in o r d e r to show
wh ich p r o p e r t i e s of the d i s t r i b u t i o n a r e r e s p o n s i b l e for the d e v i a t i o n s
t o g e t h e r wi th the v a r i a t i o n of t h e s e wi th he igh t . T a b l e 3 be low c o n
t a i n s a c o l l e c t i o n of a l l the r e s u l t s ob t a ined . In t h i s con tex t the a v e r a g e
v a l u e i s t he d i s t a n c e f r o m the e a s t e r l y z e r o poin t of the d o s i m e t e r
s e c t i o n s to t h e c e n t r e l ine of the p l u m e .
T a b l e 3 S t a t i s t i c a l p a r a m e t e r s
S e c t i o n
m
50
200
He igh t above g r o u n d
m
0. 1
2 . 0
4 . 0
6 .0
8 .0
0. 1
4 . 0
8 .0
A v e r a g e v a l u e
m
1 9 . 3
18. 3
1 8 . 6
1 8 . 6
1 8 . 0
2 9 . 8
29 . 1
3 3 . 9
Diffusion p a r a m e t e r
CTy m
6 . 3
6 . 9
7 . 0
7 . 2
7 . 7
1 5 . 0
1 5 . 3
19 .0
2 X
9 . 9 1 3
3 . 376
2 . 0 3 8
3 . 2 8 1
4 . 177
3 .588
1.772
1.351
No. of d e g r e e s of f r e e dom
14
15
16
15
14
6
6
7
R i s k l e v e l
%
23
<0 . 1
<0 . 1
<0 . 1
0 . 6
27
6
1.3
Skew
1.65
1.55
1.61
1.63
1.56
1.62
0 . 2 9
1.41
E x c e s s
0. 19
- 0 . 16
0. 14
0 . 0 7
- 0 . 2 5
- 0 . 14
0 . 2 7
- 0 . 8 3
F r o m the t a b l e i t c an be s e e n , for e x a m p l e , t ha t the c e n t r e
l ine of the d i s t r i b u t i o n a t the 50 m s e c t i o n w a s 18-19 m f r o m the
s e c t i o n ' s e a s t e r l y z e r o , and tha t the diffusion p a r a m e t e r a shows a
t e n d e n c y to i n c r e a s e wi th i n c r e a s i n g he igh t above g r o u n d . 2
The X t e s t shows t h a t the d e v i a t i o n s f r o m the n o r m a l d i s t r i b u t i o n w e r e g r e a t e s t a t g r o u n d l e v e l and r a p i d l y d i m i n i s h e d a t g r e a t e r h e i g h t s . At the 50 m s e c t i o n the r i s k l e v e l i s <0 . 1 %. R i s k
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level is defined as the r i sk of the diffusion pat tern not being normally-
dis t r ibuted. A detailed study showed that the excess var ied about z e r o ,
i. e. the dis tr ibut ion has in the main been nei ther too na r row nor too
broad. The deviation from the no rma l distr ibution found was mainly
a cer ta in posit ive skew, i . e . the dose was re la t ively g rea t e r to the
right of the centre l ine , looking in the direct ion of the wind.
Diagrams 2 and 3, pages 14 and 15 respect ive ly , show how
the dose distr ibut ions in the y-d i rec t ion compare with normal d i s
t r ibut ions .
Calculated values of the diffusion p a r a m e t e r s a and o~ r e -c y z
fer r ing to the exper iment in the Tranvik valley as well as corresponding
theore t ica l ly computed values a r e given in table 4.
Table 4 The diffusion p a r a m e t e r s cr and a , the factor I y z
X = 0 .3 36 3. 3 m / s
Distance
50 m
200 m
CTy
Studsvik-Ågesta
7.6
21.0
T ran vik
6.3
~15
CTz
Studsvik-Ågesta
3.4
8.3
Tranvik
3.8
~7
I
Studs vik -Ågesta
0.123*)
0.280*)
T ranvik
0.49
* ) Based on actual wind data for the ground layer 1,5-10 m within the tes t a r e a , an I value of 0. 36 and 0.48 respect ive ly a r e obtained. Such divergences may a r i s e as a resu l t of local effects.
The diffusion p a r a m e t e r s <j obtained from the exper iment
were somewhat smal le r than the values given by the Studsvik-Ågesta
data whilst for a roughly the same values were obtained. The mos t
noticeable difference occurs between the I - factors which for the ex
per iment were calculated on the bas is of the values obtained for o~ ,
o~ and the concentration at the plume centre l ine. z
Jose JJR
DIFFUSION FROM GROUND RELEASE
TRANVIK VALLEY 19.12.1967
Diogrom 2
-um.freq.
0,01
10 15 20 25 30 35 m
-15-Diagrom 3
DIFFUSION FROM GROUND RELEASE. TRANVIK VALLEY 19.12.1967.
Dose juR
1000 -
400-200-
Section 200 m Height 4 m
T -
0 -J—
10 - r -
30 —r~ 40 50
—r~ 60 20 70 m
Dose fsR
Section 50 m Height 4 m
2000-
1000-
i
/y
. . j— i i
NX
1 1 1 10 15 20 25 30 35 m
Experimental results
Normal distribution
- 16 -
6. 5 Plume width
The total width to a point where the dose was ze ro can only
be calculated approximately . Thus , in common with the prac t ice r e
por ted e lsewhere in the l i t e r a tu re , the width to a point where the
dose was yjy- of the dose at the centre line has been calculated. Table 5
contains values for the width of the plume expressed as ± 2cr and y
± 3Q respect ive ly , where a was obtained from the exper imenta l data.
Table 5 Plume width (met res )
Distance
50 m
200 m
F r o m the exper iment in the Tranvik valley 19. 12. 1967
yrrof the dose at
the centre line
25
80
± 2 a y
25
61
± 3 C T y
38
92
6. 6 Relative concentration, m
A compar ison has been made with those values which would
have been obtained if the calculation had been ca r r i ed out using the
appropr ia te stabil i ty p a r a m e t e r s derived from the values m e a s u r e d
at the main meteorologica l tower . The resu l t s a r e shown in d iagram 4,
page 17. Included in this d iagram a re P a s q u i l l ' s curves for stabili ty
c l a s ses A - F . The comparison shows:
1) the diffusion according to the exper iments ca r r i ed out in
the Tranvik valley was 3. 7-5.0 t imes more efficient than that
obtained theore t ica l ly from the Studsvik-Ågesta data.
2) the values fall between P a s q u i l l ' s c lass C (slightly unstable
conditions) and c lass D (neutral conditions).
3) the Studsvik-Ågesta curve (Högström) coincides approxi
mate ly with P a s q u i l l ' s class E (slightly stable conditions).
-17-
DIFRJSION FROM GROUND RELEASE
Diagram U
3 , 4 . 5 6 7 8 9 1 3 4 5 6 7 8 9 1 2 Q -V
4 5 6 7 8 9 10 4 5 6 7 8 9 io3 Distance; m i i i i i i . i i i i i i i i i i i i i i i t i i i i . i i i i i i i i i i i i i i i i i i i i i i i i t i i i i i i i i i i i i i i i i i i t i i i i i i t i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i t i t i i i i i i i t i t i i i i i i i i i t i i i i i i i i i i i i i i i i t i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i i t i i i i i i i
A
- 18 -
With r ega rd to the fact that the intention was to p resen t the
TLD and active t r a c e r method under full scale exper imenta l conditions,
and at the same t ime obtain so detailed a dose pa t te rn as poss ib le ,
the exper imenta l a r e a was selected so that a cer ta in guiding of the
wind would be brought about when passing through Trobbofjärden
and along the valley. The exper imenta l conditions were therefore
such that the resul t ing diffusion would be l ess than that calculated
theore t ica l ly .
A reason why the diffusion was in fact be t te r than that ca l
culated may be d i sc repanc ies in the wind profile between the Studs vik
site and the t e s t a r e a . (Högström, persona l communication).
Such deviations may be involved when using data from the
tower for determinat ion of local diffusion conditions at ground level .
7. RADIATION PROTECTION
7. 1 Control of safety analys is
F r o m the exper imenta l data the dose at the centre line of the
plume and a distance of 1300 m . (Tranvik farm) was found to be
0. 1 m r e m . As can be seen from the map , page 5, the plume centre
did not sweep over the Tranvik a r e a during the exper iment .
7 .2 Relationship between source strength - sampling t ime - dose
Diagram 5 r e fe r s to the distance in terva l 0. 1-1.0 km and
sampling t imes 0 .5 -5 h for two completely different weather con
di t ions, and is p resen ted in o rder to give a c l e a r e r picture of the
re la t ionship between source s trength - sampling t ime - dose when
Kr85 is used as t r a c e r . The d iagram was designed using the diffusion
formula for ground r e l e a s e s (Högström).
The following is an example of possible radiat ion exposure
for a dos ime te r , and for a pe r son respect ively in the centre of the
dos imeter section.
It is a s sumed that inversion conditions prevai l during the
exper iment so that the stabili ty p a r a m e t e r \ = 2. 5 (diagram 5:1).
- 19 -
Sampling t ime 2 h
Source s t rength 10 Ci /h
Diffusion is to be studied to a distance of 1 km
F o r the above exper imenta l conditions the following doses
should be obtained in the centre of the plume
Distance from Dose to dos imete r in Dose to humans in r e l ea se point the measur ing sections the measur ing sections
250 m ca 5600 |o,R ca 190 MPC-hours
500 m ca 1600 |iR ca 55 MPC-hours
1000 m ca 470 JAR ca 15 MPC-hours
An MPC-hour is the product of exposure t ime and the average
concentration expressed in MPC. The pe rmi s s ib l e year ly occupational
exposure expres sed in these units is 8766 MPC-hour s .
The above example implies that a person standing at the centre
of the 250 m section during the whole exper iment (2 h), rece ives about
2 % of the pe rmis s ib l e year ly dose . At a distance of 1 km, the dose
received is l e s s than 0. 02 % of the pe rmis s ib l e year ly dose to r ad io
logical worke r s i. e. 0. 2 % of the pe rmis s ib l e year ly dose to population
groups in the vicinity of a nuclear plant.
8. CONCLUSION
Diffusion exper iments with Kr85 as t r a c e r substance and (3-
sensi t ive dos ime te r s have been c a r r i e d out in the field with good
r e s u l t s . Diffusion was studied in sections at 50 m and 200 m r e spec t i ve
ly from a point r e l ea se at ground level .
The dose dis tr ibut ion was approximately normal as verif ied
by a X tes t . The p a r a m e t e r s a and a were exper imental ly de te rmined
for init ial diffusion to a distance of 200 m.
- 20 -
The maximum value for the dose and thus the relat ive concentrat ion
was de termined. Dilution factors were 3 .7 -5 .0 t imes g rea t e r than
those a r r i ved at theore t ica l ly , based on data obtained from the main
meteorologica l tower .
A safety analysis showed that the dose to a person at the plume
centre and at a distance of 1300 m, where the nea re s t fa rm is si tuated,
was 0. 1 m r e m .
The exper iment was made over snow free ground. A d i rec t
comparison will be made with the r e su l t s obtained when re leas ing
from a building.
- 2 1 - Diagram 5:1 C
one
c c
c
m c <*> C c
y._
»5
UT
I I I I o.eor^ -o
ii ils
ss Sss i : sss
::: iss
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iiii Itttfc 4
4IU4 F tffiF F 14+4 4 llnl 4
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f i r l u l l 4 4HEF4
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ss ssS | | s s |
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REFERENCES
B AR AD M L, Pro jec t P r a i r e G r a s s . Geophysical Resea rch Pape r No 59> Vol. I, II. 1958. Geophysics R e s e a r c h Di rec to ra t e . Air F o r c e Cambridge R e s e a r c h Center , Bedford, Massachuse t t s .
BARAD M L and FUQUAY J J, The Green Glow Diffusion P r o g r a m . Geophysical R e s e a r c h Pape r No 73. 1962. (AFCRL-62-251 (II), HW-71400, Vol. II . )
BJÄRNGARD B, The P r o p e r t i e s of CaSO,:Mn Thermoluminescence Dos ime te r s . 1963. (AE-109).
BJÄRNGARD B, Measurements of Small Exposures of Gamma Radiation with CaSO^Mn Radiothermoluminescence . 1963. (AE-118.)
BJÄRNGARD B, Study of Released Activity Distributions with Thermoluminescence Dos ime te r s . U.N. Internat . conf. on the peaceful uses of a tomic energy. Geneva, 3. 1964. P r o c . Vol. 14. New York 1965, p . 5.
HÖGSTRÖM U, An Exper imenta l Study on Atmospher ic Diffusion. Tellus 16 (1964) p . 205.
HÖGSTRÖM U, P e r s o n a l communication (1968).
RUDEN B-I , The Application of Thermoluminescence Dos imeters to Studies of Released Activity Dis t r ibut ions . (To be published. )
LIST OF PUBLISHED AE-REPORTS
1-280. (See the back cover earlier reports.)
281. Collision probabilities (or finite cylinders and cuboids. By I. Carlvik. 19G7. 28 p. Sw. cr. 10:- .
282. Polarized elastic fast-neutron scattering of 13C in the lower MeV-range. I. Experimental part. By O. Aspelund. 1987. 50 p. Sw. cr. 10:- .
283. Progress report 1986. Nuclear chemistry. 1967. 26 p. Sw. cr. 10:- . 284. Finite-geometry and polarized multiple-scattering corrections of experi
mental fast-neutron polarization data by means of Monte Carlo methods. By O. Aspelund and B. Gustafsson. 1967. 60 p. Sw. cr. 10:- .
285. Power disturbances close to hydrodynamic instability in natural circulation two-phase flow. By R. P. Mathisen and O. Eklind. 1967. 34 p. Sw. cr. 10:- .
286. Calculation of steam volume fraction in subcooled boiling. By S. Z. Rou-hani. 1967. 26 p. Sw. cr. 10: - .
287. Absolute E1 f A K = O transition rates in odd-mass Pm and Eu-isotopes. By S. G. Malmskog. 1967. 33 p. Sw. cr. 10:-.
288. Irradiation effects in Fortiweld steel containing different boron isotopes. By M. Grounes. 1967. 21 p. Sw. cr. 10.
289. Measurements of the reactivity properties of the Agesta nuclear power reactor at zero power. By G. Bernander. 1967. 43 p. Sw. cr. 10:- .
290. Determination of mercury in aqueous samples by means of neutron activation analysis with an account of flux disturbances. By D. Brune and K. Jir-low. 1967. 15 p. Sw. cr. 10:-.
291. Separtaion of "Cr by means of the Szilard-Chalmers effect from potassium chromate irradiated at low temperature. By D. Brune. 1967. 15 p. Sw. cr. 10:- .
292. Total and differential efficiencies for a circular detector viewing a circular radiator of finite thickness. By A. Lauber and B. Tol lander. 1967. 45 p. Sw. cr. 10:-.
293. Absolute M l and E2 transition probabilities in ' " U By S. G. Malmskog and M. Höjeberg. 1967. 37 p. Sw. cr. 10:- . V
294. Cerenkov detectors for fission product monitoring in reactor coolant water. By O. Strindehag. 1967 56 p. Sw. cr 10:-.
295. RPC calculations for K-forbidden transitions in ">W. Evidence for large inertia! parameter connected with high-lying rotational bands. By S. G Malmskog and S. Wahlbom. 1967. 25 p. Sw. cr. 10:-.
296. An investigation of trace elements in marine and lacustrine deposits by means of a neutron activation method. By O. Landström, K. Samsahl and C-G. Wenner. 1967. 40 p. Sw. cr. 10:-.
297. Natural circulation with boiling By R. P. Mathisen. 1967. 58 p. Sw. cr. 10:-. 298. Irradiation effects at 160-240°C in some Swedish pressure vessel steels.
By M. Grounes, H. P. Myers and N-E. Hannerz. 1967. 36 p. Sw. cr. 10:-. 299. The measurement of epilhermal-to-thermal U-238 neutron capture rate (p2«)
in Agesta power reactor fuel. By G. Bernander. 1967. 42 p. Sw. cr. 10:-. 300 Levels and transition rates in <"Au. By S. G. Malmskog, A. Bäcklin and B
Fogelberg. 1967. 48 p. Sw cr. 10:-
301. The present status of the half-life measuring equipment and technique at Studsvik. By S. G. Malmskog. 1967. 26 p. Sw. cr. 10:- .
302. Determination of oxygen in aluminum by means of 14 MeV neutrons with an account of flux attenuation in the sample. By D. Brune and K. Jlrlow 1967. 16 p. Sw. cr. 10:-
303. Neutron elastic sca'tering cross sections of the elements Ni, Co, and Cu between 1.5 and 8.0 mev. By B. Holmqvlst and T. Wledling. 1967. 17 p Sw. cr. 10:- . r
304. A study of the energy dependence of the Th232 capture cross section in •he energy region O.I to 3.4 eV. By G. Lundgren. 1967. 25 p. Sw. cr. 10:-.
305. Studies of the reactivity effect of polythene in the fast reactor FRO. By L. I. Tirén and R. Håkansson. 1967. 25 p. Sw. cr. 10:- .
306. Final report on IFA-10, the first Swedish instrumented fuel assembly Irradiated in HBWR, Norway. By J-A. Gyllander. 1967. 35 p. Sw. cr. 10:-.
307. Solution of large systems of linear equations with quadratic or non-quadratic matrices and deconvolution of spectra. By K. Nyqaard. 1967. 15 o. Sw. cr. 10:- . r
308. Irradiation of superheater test fuel elements in the steam loop of the R2 reactor. By F. Ravndal. 1967. 94 p. Sw. cr. 10:- .
309. Measurement of the decay of thermal neutrons in water poisoned with the non-1/v neutron absorber cadmium. By. L. G. Larsson and E. Möller. 1967. 20 p. Sw. cr. 10:-.
310. Calculated absolute detection efficiencies of cylindrical Nal (Tl) scintillation crystals for aqueous spherical sources. By. 0 . Strindehag and B. Tollander. 1988. 18 p. Sw. cr. 10:- .
311. Spectroscopic study of recombination in the early afterglow of a helium plasma. By J. Stevefelt. 1968. 49 p. Sw. cr. 10:- .
312. Report on the personnel dosimetry at AB Atomenergi during 1966. By J. Carlsson and T. Wahlberg. 1968. 10 p. Sw. cr. 10: - .
313. The electron temperature of a partially ionized gas in an electric field. By F. Robben. 1968. 16 p. Sw. cr. 10:-.
314. Activation Doppler measurements on U238 and U235 in some fast reactor spectra. By L. I. Tirén and I. Gustafsson. 1968. 40 p. Sw. cr. 10: - .
315. Transient temperature distribution in a reactor core with cylindrical fuel rods and compressible coolant. By H. Vollmer. 1968. 38 p. Sw. er. 10:- .
316. Linear dynamics model for steam cooled fast power reactors. By H. Vollmer. 1968. 40 p. Sw. cr. 10:- .
317. A low level radioactivity monitor for aqueous waste. By E. i. M. Ouirk. 1968. 35 p. Sw. cr. 10: - .
318. A study of the temperature distribution in UOi reactor fuel elements. By I. Devoid. 1968. 82 p. Sw. cr. 10:- .
319. An on-line water monitor for low level ^-radioactivity measurements. Bv E. J. M. Quirk. 1968. 26 p. Sw. cr. 10:- .
320. Special cryostats for lithium compensated germanium detectors. By A. Lauber, B. Malmsten and B. Rosencrantz. 1968. 14 p. Sw. cr. 10: - .
321. Stability of a steam cooled fast power reactor, its transients due to moderate perturbations and accidents. By H. Vollmer. 1968. 36 p. Sw. cr. 10:- .
322. Progress report 1967. Nuclear chemistry. 1968. 30 p. Sw. cr. 10: - . 323. Noise in the measurement of light with photomultipliers. By F. Robben.
1968. 74 p. Sw. cr. 10:- .
324. Theoretical investigation of an electrogasdynamic generator. By S. Palmgren. 1968. 36 p. Sw. cr. 10:- .
325. Some comparisons of measured and predicted primary radiation levels in the Agesta power plant. By E. Aalto, R Sandlin and A. Krell. 1968. 44 p. Sw. cr. 10:-.
326. An investigation of an irradiated fuel pin by measurement of the production of fast neutrons in a thermal column and by pile oscillation technique. By Veine Gustavsson. 1968. 24 p. Sw. cr. 10:- .
327. Phytoplankton from Tvären, a bay of the Baltic, 1961-1963. By Torbiörn Willén. 1968. 76 p. Sw. 10:- .
328. Electronic contributions to the phonon damping in metals. By Rune Jonson. 1968. 38 p. Sw cr. 10:- .
329. Calculation of resonance interaction effects using a rational approximation to the symmetric resonance line shape function. By H. Häggblom. 1968. 48 p. Sw. cr. 10:- .
330. Studies of the effect of heavy water in the fast reactor FRO. By L. I. Tirén, R. Håkansson and B. Karmhag. 1968. 26 p. Sw. cr. 10:-.
331. A comparison of theoretical and experimental values of the activation Doppler effect in some fast reactor spectra By H. Häggblom and L. I. Tirén. 1968. 28 p. Sw. cr. 10:-.
332. Aspects of low temperature irradiation in neutron activation analysis. By D. Brune. 1968. 12 p. Sw. cr. 10:- .
333. Application of a betatron in photonuclear activation analysis. By D. Brune, S. Mattsson and K. Liden. 1968. 13 p. Sw. cr. 10: - .
334. Computation of resonance-screened cross section by the Dorix-Speng system. By H. Häggblom. 1968. 34 p. Sw. cr. 10: - .
335. Solution of large systems of linear equations in the presence of errors. A constructive criticism of the least squares method. By K. Nygaard. 1968. 28 p. Sw. cr. 10:- .
336. Calculation of void volume fraction in the subcooled and quality boiling regions. By S. Z. Rouhani and E. Axelsson. 196B. 26 p. Sw. cr. 10:- .
337. Neutron elastic scattering cross sections of iron and zinc in the energy region 2.5 to 8.1 MeV. By B. Holmqvist, S. G. Johansson, A. Kiss, G. Lodin and T. Wiedling. 1968. 30 p. Sw. cr. 10:-.
338. Calibration experiments with a DISA hot-wire anemometer. By B. Kjell-ström and S. Hedberg. 1968. 112 p. Sw. cr. 10:—.
339. Silicon diode dosimeter for fast neutrons. By L. Svansson, P. Swedberg, C-O. Widell and M. Wik. 1968. 42 p. Sw. cr. 10:- .
340. Phase diagrams of some sodium and potassium salts in light and heavy water. By K. E. Holmberg. 1968 48 p. Sw. cr. 10:- .
341. Nonlinear dynamic model of power plants with single-phase coolant reactors. By H. Vollmer. 1988. 26 p. Sw. cr. 10:-.
342. Report on the personnel dosimetry at AB Atomenergi during 1967. By J . Carlsson and T. Wahlberg. 1968. 10 p. Sw. cr. 10:-.
343. Friction factors in rough rod bundles estimated from experiments in partially rough annul! - effects of dissimilarities in the shear stress and turbulence distributions. By B. Kjellström. 1968. 22 p. Sw. cr. 10:- .
344. A study of the resonance interaction effect between "«U and "'Pu in the lower energy region. By H. Häggblom. 1968. 48 p. Sw. cr. 10: - .
345. Application of the microwave discharge modification of the Wilzbach technique for the tritium labelling of some organics of biological interest. By T. Gosztonyi. 1968. 12 p. Sw. cr. 10: - .
346. A comparison between effective cross section calculations using the intermediate resonance approximation and more exact methods. By H. Häggblom. 1969. 64 p. Sw. cr. 10: - .
347. A parameter study of large fast reactor nuclear explosion accidents. By J. R. Wiesel. 1969. 34 p. Sw. cr. 10:- .
348. Computer program for inelastic neutron scattering by an anharmonic crystal. By L. Bohlin, I. Ebbsjö and T. Högberg. 1969. 52 p. Sw. cr. 10: - .
349. On low energy levels in " ! W . By S. G. Malmskog, M. Höjeberg and V. Berg. 1969. 18 p. Sw. cr. 10:- .
350. Formation of negative metal ions in a field-free plasma. By E. Larsson. 1969. 32 p. Sw. cr. 10:- .
351. A determination of the 2 200 m/s absorption cross section and resonance integral of arsenic by pile oscillator technique. By E. K. Sokolowski and R. Bladh. 1969. 14 p. Sw. cr. 10:- .
352. The decay of "<Os. By S. G. Malmskog and A. Bäcklin. 1969. 24 p. Sw. cr. 10: - .
353. Diffusion from a ground level point source experiment with thermolumine-scence dosimeters and Kr 85 as tracer substance. By Ch. Gyllander, S. Hollman and U. Widemo. 1969. 23 p. Sw. cr. 10:- .
List of published AES-reports (In Swedish)
1. Analysis be means of gamma spectrometry. By D. Brune. 1961. 10 p. Sw. cr. 6:- .
2. Irradiation changes and neutron atmosphere in reactor pressure vessels-some points of view. By M. Grounes. 1962. 33 p. Sw. cr. 6:—.
3. Study of the elongation limit in mild steel. By G. Östberg and R. Atter-mo. 1963. 17 p. Sw. cr. 6:- .
1. Technical purchasing in the reactor field. By Erik Jonson. 1963. 64 p. Sw. cr. 8 : - .
5. Agesta nuclear power station. Summary of technical data, descriptions, etc. for the reactor. By B. Lilliehöök. 1964. 336 p. Sw. cr. 15:- .
6. Atom Day 1965. Summary of lectures and discussions. By S. Sandström. 1966. 321 p. Sw. cr. 15:-.
7. Building materials containing radium considered from the radiation protection point of view. By Stig O. W. Bergström and Tor Wahlberg. 1967. 26 p. Sw. cr. 10:- .
Additional copies available from the library of AB Atomenergi, Fack, S-611 01 Nyköping, Sweden.
EOS-tryckerierna, Stockholm 1969