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Atomic Energy of Canada Limited
FLUX DISTRIBUTION MEASUREMENTS
m THE GENTILLY REACTOR
by
A. OKAZAKI, D,H. WALKER and M.H.M.ROSHD
Chalk River, Ontario
July 1971
AECL-3962
Mesures de distribution des flux dans le réacteur Gentilly
par
A. Okazaki et D.H. WalkerChalk River
et
M.H.M. RoshdGroupe électronucléaire
Résumé
Ce rapport décrit les mesures des distributionsaxiales et radiales des flux neutroniques, effectuées paractivation de fils de cuivre durant la mise en service àfaible puissance du réacteur BLW de Gentilly. Les distri-butions radiales ont été mesurées dans une barre desurréactivité vide placée parallèlement au diamètre est-ouestdu réacteur et séparée de lui par un pas de réseau, tandisque les distributions axiales ont été mesurées dans un dédétecteur de flux situé à quatre pas de réseau de la lignecentrale du réacteur. Des dispositifs de balayage munis dedétecteurs à scintillations Nal ont été employés pourdéterminer l'activité des fils. Les distributions ont étéobtenues avec et sans eau légère de caloportage dans lescanaux de combustible et pour divers arrangements de barresd'absorption et de surréactivité. Les points de fluxmontrent les basculements associés de flux.
L'Energie Atomique du Canada, Limitée
Laboratoires Nucléaires de Chalk River
Chalk River. Ontario
AECL-3962
FLUX DISTRIBUTION MEASUREMENTS IN THE
GENTILLY REACTOR
by
A. Okazaki and D.H. WalkerChalk River Nuclear Laboratories
and
M.H.M. RoshdPower Projects^
A B S T R A C T
This report describes the radial and axial neutronflux distribution measurements made by copper wire activationduring the low power commissioning of the Gentilly BLW reactor.The radial distributions were measured in an empty boosterrod tube located parallel to, and one lattice pitch from, theE-W diameter of the reactor, while the axial distributionswere measured in a flux detector thimble four lattice pitchesfrom the reactor center line. VJire scanners with Nal scin-tillation detectors were used to determine the wire activity.Distributions were obtained with and without light watercoolant in the fuel channels and for various absorber andbooster rod configurations. The flux plots show the associatedflux tilts.
Chalk River Nuclear LaboratoriesChalk River, Ontario
July, 1971
AECL-3962
CONTENTS
1. INTRODUCTION
2. EXPERIMENT2.1 Location of Wires 12.2 Irradiation 22.3 Counting Equipment 3
3. COUNTING RESULTS3.1 Reduction of Counting Data 43.2 Counter Efficiency 43.3 Relationship of Flux to Activity 53.4 Stretching of Wire 6
4. PLOTS OF THE DISTRIBUTIONS4.1 Location of Points 7
5. RESULTS 75.1 Axial Distributions 85.2 Extrapolated Height 105.3 Radial Distributions 10
6. SUMMARY 12
7. ACKNOWLEDGMENTS 12
FLUX DISTRIBUTION MEASUREMENTS IN THE
GENTILLY FACTOR
1. INTRODUCTION
The Gsntilly reactor is a 250 MWe heavy water moderated
natural uranium fuelled, boiling light water fooled reactor,
which went critical in November 1970. During the low power
Phase B commissioning, physics measurements were made to
check, design calculations and to provide information for the
design of future power reactors. This report describes the
axial and radial neutron flux distributions measured for
various configurations of booster and control rods. The
experiment was carried out in collaboration with members of
the Physics and Analysis Branch o± Power Projects, who proposed
the experiment and devised the methods of insertion and removal
of the copper wire deteecors in the reactor. The provision
of the counting equipment and the activity measurements of the
irradiated wires were the responsibilities of the Reactor
Physics Branch of the Chalk River Nuclear Laboratories.
2. EXPERIMENT
2.1 Location of Wires
The neutron flux distributions were measured by activation
of 1.63 mm diameter bare annealed copper wires placed in the
reactor.
2.1.1 Radial
The radial distribution was measured in an air-filled
booster rod tube (position 7-8) shown in Fig. 1. The wire
passed through a special 2.54 cm ID aluminum tube located con-
centrically in the booster tube. For insertion the following
-2-
procedure was used. The copper wire vras attached to and
wound on a spool placed on a table outside the west face
of the reactor (see Fig. 2) . A string was attached tr a
small wooden plug, which was then blown through the tube
• from the east side with an air hose. The string was at-
tached to the copper wire at the west side. The wire was
then pulled into the reactor by winding the string on the
east spool driven by an electric hand drill. A 2.3 kg
v/eight was attached to the wire to keep it taut during the
irradiation. At the end of the irradiation period the wire
was cut at the west end face of the booster tube and wound
on the east spool with the electric drill.
2.1.2 Axial
The axial distributions were measured in the air-filled
in-core flux detector thimble located at KL 14-15 (see Fig.
1) . The flux detector had been removed for these experiments.
In a few experiments the axial distribution was alsc measured
in the start-up counter thimble located at PQ18-19 at the
edge of the reactor core.
The copper wire was inserted in a small aluminum tube,
about 550 cm long, which in turn was attached to a string,
which passed through a ring attached to an overhead crane
as shown in Fig. 3. At the start of irradiation the wire
was lowered to the bottom of the thi^le^ and at the end cf the
irradiation was removed by pulling the string as quickly as
•. p o s s i b l e . ....•-••',,•
2.2 Irradiation
In Experiments1 and 2 the wires were inserted and removed
with thereactor shut down while for the other experiments
these were done with the reactor at steady power. The inser-
tion and removal each took less than 8 seconds. The conditions
-3-
for the irradiations are listed in Table 1. The times
at the start of insertion and removal and the time in the
reactor are given. The log power readings of the three
control ionization chambers were taken from the reactor
data sheets where available. These have been converted to
relative linear powers, P/Po» where log Po has arbitrarily
been chosen equal to - 4.790.
The axial and radial wires were irradiated simultan-
eously in all experiments except Expt. 16. Thus the irradia-
tion times given for Expt. 16 are nominal but are estimated
to be within .2 minutes. As noted in Table 1 the times for
some other experiments were not measured accurately but are
probably better than 1 minute.
2.3 Counting Equipment
The activity of the irradiated wires was measured v.ith
two wire" scanners, one-of which is shown in Fig. 4. The Cue4
gamma rays with energy greater than 66 kev were detected with
a 5.1 cm diameter 2.54 cm thick Nal (TJ£) scintillation counter
mounted in the Pb shielding. The Nal crystal views the copper
wire through a 1 cm wide slotted collimator, which can be
seen in Fig. 5. The details of the shielding are shown in
Fig. 6.
The irradiated copper wires were cut into 139.7 cm lengths.
Brass rods were soldered to each end of the wire and were
then clamped in the scanner carriage. The carriage was driven
across the top of the detector by a rack and pinion, whose
drive motor was started by a signal from the automatic control
unitand stopped by a signal from a microswitch actuated by
screws spaced at 1.397 cm intervals on the carriage. Counts
, were made at 91 points fat 1^397 cm intervals with the first and
-4-
last points 6.99 cm from the endsof the wire. The ver-
tical position of the wire above the collimator was fixed
by two bar guides attached to the collimator, and the
lateral position by two pins on the shield lid. These can
be seen in Fig. 5.
A block diagram of the counting system is given in
Fig. 7. Both wire scanners were controlled by the one auto-
matic control unit. The statistical accuracy of the counting
was better than 1% except in the low activity parts of"the
wires which had been in the shielding.
3. COUNTING RESULTS
3 .1 Reduction of Counting Data
" . The measured counting"rates were corrected for room
background and for radioactive decay to obtain the counting
rate C, at time t after the end of irradiation. Each distri-
bution has been normalized to unity at the maximum activity and
the normalized activities A, are plotted where
i \ max I
and'i'C • = ̂maximum activity.
3 .2 .Counter' Efficiency
The wires were measured with two counters. Since not
all the 139J7 cm lengths from one distribution were counted
on the same counter it was necessary to determine the
relative .fefficiencies by counting some wires on both counters.
For Expt.' 1-4/ the ratio of the efficiencies of -punter 2 to
' counter 1 was 1.034 +.0.002 and for Expt. 5-'.9.it was 1.014 +..
-,. . / 0.002.
-5-
3.3 ' Relatioriship of Flux to Activity
The measured distribution of activity along a wire
gives the spatial distribution of neutron flux in the
reactor.- ̂lTp5:Cpmpar.e.v--fehe.••̂•f:lux levels in the different experi-
ments one musjt take into account the different irradiation
times, the time after the end of irradiation, reactor power
and the counter efficiency.
The counting rate CQ, that would have been obtained
for an irradiation time T Q and ion chamber reading Po, is
given by
= C (-f U . e -AT (2)
where C = counting rate at time t after the end of irradiation,
T = irradiation time,
and P = regulation ion chamber reading.
This counting rate is related to the neutron flux by
where
and
Then
X = Cu64 decay constant
N = number of atoms in length of wire in the counter
: collimator,
a = Cu63activation cross section,
tf = neutron-flux
rQ = irradiation time,
t = time after end of irradiation,
e = counter efficiency,
8 = stretch factor for the copper wire.
7vNa(l -
-6-
The flux can be expressed in terms of the normalized activity
by replacing C using the relations given in equations 1 and 2
*tep C A /Po\A " e, K max ' *'
ANff(l - e XO)S
_ K cmax D A
where K =
D .
E
ANa(l - e
As defined in Equation (3), jzf is the flux when the reactor
power indicated by the ion chambers is PQ. The relative values
of ^, i.e. (IT) can be obtained by multiplying the normalized
activity A, shown in the plots, by the factors which, are also
given on.the plots and in Tables 1 and 2. The efficiency e is
the relative efficiency and is unity for counter 1. The stan- .
dard conditions were T Q = 1200 seconds and the average value
for the three ion chambers of log P o = - 4.790.
3.4 Stretching of Wire
Before cutting and counting, the irradiated wires were
pulled to straighten and to eliminate the kinks caused by
winding the wires after the.irradiation. This pulling resulted
in stretching the wires. The amount of stretch was determined
by weighing the wires after counting and comparing with the
mass of the same length of unstretched wire. The stretch factor
3 is defined as the ratio of the masses of the unstretched
\ to that of the stretched wire and is also equal to the ratio
-7-
of the stretched length to unstretched length. It is
assumed that the stretch is uniform along the length of
the wire. The stretch factors which are listed in Table 2,
ranged up to 1.078 for the Expt. 16 axial wire. The change
in the self absorption of the gamma rays in the wire is less
than 0.3%, which is less than the uncertainty in the counting,
and has been neglected.
4. PLOTS OF THE DISTRIBUTIONS
4.1 Location of Points
As discussed in Section 2.3, the activity of the wires
was measured at 1.397 cm intervals. However, because of the
stretching of the wires, these intervals correspond to1.397 . ..—— cm in the reactor.P
4.1.1 Radial
There are flux peaks in the radial distributions at posi-
tions midway between fuel channels and minima opposite the
fuel channels. In the plots the radial position of the wire
was shifted so that the peaks are symmetric about the reactor
center
4.1.2 Axial
The bottom end of the axial wire in position KL14-15 was
8.41 cm above the calandria floor. For the plots in position
PQ18^1? it was assumed that the end of the wire was at the
same elevatipn. -
5. - RESULTS
Measurements were made for 19 experiments with various
control absorber and booster rod configurations to study
flux tilt and to calibrate the absorber and booster reactivity
worths. The positions of the absorbers and booster banks,
-8-
boron concentration in the moderator, inlet temperatures
of the two coolant circuits, moderator temperature and height
are listed in Table 3. The fuel channels were filled with
full density light water coolant except in Expt. 1 when there
was no coolant, in Expt. 18 when one coolant circuit was half
full, and in Expt. 19 when one coolant circuit was empty.
There are two coolant circuits, each circuit being connected
to alternate W-S rows of fuel channels. The booster rods in
each bank and the location of the absorber rods are listed
in Table 4.
The plots of the axial and radial distributions are shown
in Fig. 8-25 and Fig. 27-39 respectively.
5.1 Axia1 Di stribut ion s
In all the distributions there is a break at the moderator
surface. In Expt. 5-18 with the full moderator height there
is a break at the moderator surface at 500 -cm elevation. The
flux is almost flat in the helium space above the moderator,
then decreases sharply in the top thermal shield. There is
a change of scale in the plots at the top end where the points
with normalized values less than 0.01 are multiplied by 50.
(i) Expt. 1 (Fig. 8): There was no coolant in the fuel channels
andthe absorbers were well above the moderator level.
The distribution in PQl8^l9 is apparently shifted to
lower elevations than in KB14-15 indicating that the wire
was actually higher than assumed,
(ii) Expt. 2 (Fig. 9): Full density light water coolant was
in the fuel channels. The absorbers were still above
the moderator,
(iii) Expt. 3 (Fig. 10): The axial distribution in KL14-15
is no longer symmetric about the maximum/ beingdepressed
-9-
in the upper part by the absorbers whose lower ends
were at 250 cm elevation. The distribution in PQ18-19
which is near the edge of the reactor core and far from
the absorbers is only slightly affected by them.
(iv) Expt. 4 (Fig. 11): These are similar to Expt. 3 except
the moderator was at 493.2 cm.
(v) Expt. 5 (Fig 12) : During the irradiation the absorbers
were moving between 93% and 95% insertion. The wire
at KL14-15 wai not fully inserted as clearly shown in
the plot. In Expt. 5-19, the moderator was at full
height.
(vi) Expt. 6 (Fig. 13) : This was a repeat of Expt. 5 but
with the absorbers steady,
(vii) Expt. 7-12 (Fig. 14-19): Measurements of flux tilts
with various absorber configurations.
(viii) Expt 7 (Fig. 14) : Absorber #3 located two lattice
pitches (55.9 cm) away was withdrawn and comparison
with Expt. 6 shows that the flux is not depressed as
much,
(ix) Expt. 13-17 (Fig. 20-24): Measurements for various
configurations of booster rods,
(x) Expt. 18 (Fig. 25): One coolant circuit was half full.
As noted above there is a sharp break in the flux distri-
bution at the top thermal shield. The elevation of this break
was determined by plotting the upper part of the axial distri-
bution on an expanded scale as illustrated in Fig. 26. The
results listed in Table 2 are in reasonable agreement with the
520.7 cm elevation of the bottom of the top thermal shield
arid show that the stretch corrections are valid.
-10-
5.2 Extrapolated Height
The axial distributions of Expt. 1 and 2, which are
not perturbed by the absorbers, were fitted by the method
of least squares to the function A(z) = B cos = (z - zQ),
where <* = — }
n
H = extrapolated height,
z = elevation above the calandria floor,
and zQ = elevation of the maximum.
The fitted parameters and the measured critical heights are
given in Table 5. The uncertainties quoted are based on the
•goodness of fit1 . Also given are the total, upper and lower
extrapolation lengths derived from the results. In Expt. 1
the extrapolated height obtained from the distributions in
the two locations agree within the accuracy of the fits. The
apparent shift of PQ18-19 downward relative to KL14-15 arises
because the elevation of the wire in PQ18-19 was higher as
discussed in Section 5.1. The extrapolation lengths are the
same within the accuracy of the least squares fit.
5 .3 Radial Distributions
In the radial distribution plots the positive radii are
in the east direction. There are peaks at mid-cell locations
and minima opposite the fuel channels. The peak at the reactor
center is missing, the result of the flux depression caused
by the thick Zircaloy section joining the two booster tubes
from each side. The flux decreases in the heavy water reflector
beyond the last fuel channel, which is located 265.4 cm from
the reactor center, becomes flat in the He-filled dump annulus,
and finally should decrease in the reactor shield. This final
decrease is seen only in Expt. 2. Beyond 340 cm radius where
the normalized activity is less than 0.01, the activity has been
multiplied by 100.
-11-
In Expt. 1 and 2 the insertion and removal of wires
from the reactor were made while the reactor was shut down.
In all other experiments the wires were inserted and withdrawn
when the reactor was at steady power. All parts of the wire
passed through the reactor and hence were exposed to neutrons
during insertion and removal. This was in addition to the
irradiation received while it was stationary in the reactor.
Thus the flux levels in the dump annulus and reactor shield
are reliable only for Expt. 2.
An estimate can be made of the contribution to the
activity during transit. The time from the start signal to
completion of insertion or removal was less than 8 seconds.
The actual travel time is thought to be much less than this.
Since the diameter of the calandria is 712 cm and the total
distance travelled by the wire is about 1500 cm, the time712 x 8
spent in the calandria is less than — = 3 . 8 sec.
The average normalized activity in the calandria is about 0.6.
Thus for an irradiation time of 1200 seconds the ratio of
integrated flux during the trans it to that in the maximum
flux during the irradiation isf̂ jfo) M 3 2 x 10~3 . The
activity in the dump annulus in Expt. 2 is about 1 x 10 and
since the wire was inserted and removed with the reactor shut
down, this should be the correct activity in the annulus. In
Expt. 33 14 and 15 the activity in the annulus is also about
1 x 10 ~a, and in Expt. 5 is 0.6 x lo"3 . Thus it is clear that
the estimated activity induced during the transit is an
overestimate. From the results of the other experiments it—3
appears that the transit contribution is about 0.5 to 1 x 10 ,
which would correspond to a transit time through the calandria
of about 1 to 2 seconds. This is consistent with the approximate
maximum time of 3.8 seconds given above.
-12-
During the insertion in Expt. 7, the end of the wire
came off the west spool but was recovered and tied to a
bar. The part of the wire which is normally in the annulus
was probably inside the calandria during the recovery period
and was exposed to a higher neutron flux. This is the likely
explanation for the apparent gradient measured in the annulus.
The'radial distributions in Expt. 2-5, 8, 16 and 17 are
symmetric about the reactor center. The other distributions
are asymmetric because of the asymmetric configuration of
absorber and booster rods, and in Expt. 19 because one coolant
circuit was empty.
6. SUMMARY
This report summarizes the results of the measurements
of the radial and axial flux distributions made near the center
of the Gentilly reactor core during the low power Phase B
commissioning. The measurements extended into the reactor
shields and were made with sufficient detail (about 1.35 cm
spacing) to show the fine structure in the neutron flux in the
vicinity of the fuel channels.' The plots of the distributions
show clearly the flux tilts produced by the various absorber
and booster rod configurations and voiding of one coolant
circuit.
7. ACKNOWLEDGMENTS
We jwish to acknowledge the assistance of personnel at
CRNL and at the Gentilly Nuclear Power Station. In particular
we wish to acknowledge the invaluable assistance of D.A. Kettner
in- the preparation and setting up of the equipment, and in
the irradiation and counting of wires. Dr. L.F. Monier, the
-13-
Phase B Co-ordinatdrj assisted in the design of the experiment
and arranged for on-site assistance. D.Miller (Power Projects)
helped in the insertion and removal of wires from the reactor.
The mechanical parts of the wire scanners were made at CRNL
by J. Weaver. Mrs. A. Brum ran the counting rate reduction
program. The plotting program was written by D.G. Stewart,
and Mrs. E.A. Okazaki gave advice on the running of the
program. We also wish to thank Dr. L.F. Monier for providing
the translation of Figure 1 and Hydro-Quebec for permission
to reproduce this drawing.
TABLE! 1 IRRADIATION CONDITIONS
EXPT
1
2
3
A
5
6
7'
8
9
10
u12
13
14
15
16
17
18
19
DATE
NOV
NovNov,
Nov.
NOV.
Nov.
NOV.
NOV.
Hov.
Nov.
Nov.
Nov.
Nov.
Nov.
Nov.
NOV.
Nov.
Nov,
Nov,
13
16
17
17
IB18
IB.
19
20
23
23
24
24
24
24
25
23
26
27
IN
I61SI14:04
,; 20,19
10i4917iO923.4523i4600)3816130
17:15
01:2011:1015:0520:0605:15
18:16
01:07
IRRADIATION
OUT
19I441"
14:35
20:4411:2517:3000:1000:0700:58
16:4717:32
01:3511:3215:2720:2405:4018:35
01:37
TIME(seel
1P.B5
1510
2100
12601500120012001020
1020
(900*(1320)*132010801500*1200
1800
CHANNELA
- 4
-4
-4
- 4
- 4 .
- 4 .
- 4 ,
- 4 .
- 4 ,
- 4 .
- 4 ,
- 4 .
- 4 .
- 4 .
- 4 .
- 5 .
807
829
827
813
845
843
791
803
797
623
937
790
782
627
854
303
LOG 9
CHANNEL
n
-4
- 4
-4
- 4
- 4
- 4
-4
- 4
-4
- 4
-4
- 4
- 4
- 4
- 4
-5
.703
.733
.731
.719,702.724.749.753
.792
.728
.576,70 7.702.780
.790
,170
CHANNELC
-4,764
-4.789-4.789-4,790-4 .789-4.791-4.81B-4,799-4.834
-4,790-4.790-4,959-4.943-4,790-4.776
-5.281
MEAN
-4
-4
- 4
-4
- 4
-4
- 4
-4
- 4
- 4
-4
' -4
- 4
-4
-4
-5
.764
.789
.789
.789
.789
.791
.791
,797
.797
.791
.790,790.782.790,790
.283
CHANNELA
0 . 9 6 2
0.914
0.9180.9480.8810.9020.998
0,9710,984
0.9270.7131,0001.0190.9180.863
0,307
P/Po
CHANNELB
1 , 2 2 2
1.1401,1461.1781,2251.164
1.0991.089
0.9951.1541.63 71,2111.2251.023
1.000
0,417
r
**
CHANNELC
1.0621.0021.0021.0001.0020.9980.9380.980
0.904
1.0001.0000.6780.7031.000 .1.033
0.323
MEAN
1.0631.0021.0021.0021.0020.9980.9980.9840.984
0.9981,0001.0001.0191.0001,000
0.321
1,302
2.462
1.6281.1732.3343.7593.586
1,613
1.549
1.004
0.5870.4760.3640.22100.1102
0.0754
D
0,785
1.9560,9351.1151.8673,7683.595
1.926
1.8501.3390,5340.433
0.3970.1772
0,1102
0.1572
+, Wire inserted and removed with reactor shut aown.•ft Axial and radial wires inserted and removed at different times* Irradiation time not known accurately.
** Log Po —4.790
- 15 -
TABLE 2
STRETCH FACTOR
EXPT.
1
2
3
4
5
6
7
8
9
10
11
12
13
14
15
16
17
18
19
RADIAL
P
-
-
1.0051
1.0128
-
1.0100
-
1.0120
-
-
1.0103
1.0147
1.0122
-
-
• . -
. 1.0140
1.0232
1.0315
1.0412
1.0216
-
1.0335
Spacing(cm)
_
-
1.3889
1.3793
-
1.3832-
1.3804
-
-
1.3828
1.3768
1.3802-
-
-
1.3777
1.3653
1.3543
1.3417
1.3675
-
1.3517
Posit ion
KL14 -
PQ18 -
KL14 -
KL14 -
PQ18 -
KL14 -
PQ18 -
KL14 -
PQ18 -
KL14 -
KL14 -
KL14 -
KL14 -
KL14 -
KL14 -
KL14 -
KL14 -
KL14 -
XL14 -
KL14 -
KL14 -
KL14 -:
;
15
1 9
15
15
1 9
15
19
15
19
15
15
15
15
15
15
15
15
15
1 5 -
15
15
15
AXIAL
P
0.9998
0.9998
1.0009
1.0367
1.0302
1.0192
1.0145
1.0187
1.0082
1.0060
1.0247
1.0195
1.0072
1.0203
1.0275
1.0146
1.0193
1.0417
1.0210
1.0777
1.0268
-1.0349
-
Spacing(cm)
1.3970
1.3970
1.3957
1.3476
1.3560
1.3707
1.3770
1.3713
1.3856
1.3886.
1.3633
1.3702
1.3871
1.3692
1.3597
1.-3770
1.3705
1.3411
1.3682
1.2963-
1.3605
1.3499
-
A OpShield
(cm)
_
-
-
-
521.5
512.2
(463.6)*
515.2
521.0
519.4
520.0
520.0
520.2
520.7
520.7
520.0
520.2
518.9
-
519.7
518.6
»._"_This wire was not fully inserted.
...I -^•«-— vt-
T2BLE 3 REACTOR CONDITIONS
CXPT
1
2
3
4
5
6
7
C
9
10
11
12
i314
15
16
17
18
19
DATE
Nov.
NOV.
NOV.
Nov.
Nov.
• Nov.
Nov.
Nov.
Nov.
Nov.
Nov.
Nov.
Nov.
Nov.
Nov.
Nov.
Nov.
Hov.
Nov.
13
16
17
17
18
18
18
19
20
23
23
24
24
24
24
25
25
26
27
1
95
95
95 ,
94
96
95
67
66
G2
63
2
95
95
95
94
ABSORBER (% INSERTION)
3 4 5
95 95 95
95 95 95
95 95 95
94 94 94
6
95
95
95f
H:Moving between 93 and 95%
96
95
67
CG
62
5
96 95 95
95 3 95
67 67 67
98 97 66
62, 95 63
98 97 98
Mean = 18%
Mean =71%
Mean, = 67%
Mean'= 68%
Mean = 68%
Mean = 65%
Mean = 71%
95
94
67
4
62
6
a
7
95
95
:.95 '
94
95
94
67
4
5
5
BOOSTER BANK •(cm)
1
0
0
0
0
0
0
0
0
0
0
0
0
0
232
330
330
330
3 •
2
0
0
0
0
0
0
0
0
0
0
0
0
0
0
0
330
330
3
3
0
0
0
0
0
0
0
0
0
0
0
0
330*
0
0
0
300
••2 •
BORON
(ppm)
0
0
3.42
3.50
3.67
3.67
3.67
3.67
3.93
4.09
•4.40
5.01
6.20 .
: :;:7.75 •
j 7.75
10.89
COOLANT INLETTEMPERATURE (°C)
Header 1
9.9
10.2
9.8
10.4
9.7
9.6
9.6
13.5
12.5
<3.7
8.9
8.9
header 2
13.;i
13.3
13.0
13.6
12.7
13.0
12.9
17.3
16.1
13.0
11.9
11.9
MODERATCHTEMPERATURE
(CC)
24.5
24.7
24.7 '
24. 7
24.9
24.8
25.3
25.3
25.3
25.3
25.3
25.3
25.3
25.3
25.3
O"1
1i
I• Booster rod 3 only.
- 17 -
TABLE 4
BOOSTER BANKS AND ABSORBERS
Bank
1
2
33
Boosters
Booster Rod
1,2,5,6,11,12
6,15,9,10
3,4,13,14
No.
1
2
3
4
5
6
7
Absorbers
Location
KL10-11
OP10-11
MN14-15
HJ14-15
FG10-11
HJ6-7
MN6-7
TABLE 5
LEAST SQUARES FIT
TO AXIAL DISTRIBUTIONS
Region fitted (cm)
oc (ra~ )
z o (cm)
H (cm)
Measured Hc (cm)
6H (cm)
5Hu(cm)
5HL(cm)
EXPT.
KL 14-15
31 - 110
2.007 ± 0
69.97 ± 0
156.5 ± 1
139.4 ± 1
17.1
8 . 8
8 . 3
021'
24
7
1
PQ18-19
31 - 110
2.025 ± 0.016
62.74 ± 0 . 2 1
155.1 ± 1.2
139.4 ± 1
15.7
0.9*
* 14. 8*
EXPT. 2
KL 14-15
31 - 194
1.309 ±0.001
113.43 ± 0.05
240.0 ± 0 . 2
224 ± 1
16.0
9 . 4
6 . 6
00I
* As discussed in Section 5.1, the elevation of the wirewas higher than assumed.
UMNO
Page 19
Figure 1: Gentilly reactor core.
O <D O O O 0 C?—12 N*(B-Q CD -13 s
Q Q Q G COMPUTE* LIMIT - K > »
LOWE* UMIT SWITCH - I O * T — zLOMEf) MECHAMOLSTOF — I C H
DIAGRAMMATIC SECTION
REACTOR CENTER LINE
/
BOOSTER DRIVE
PULLEY
COPPER WIRE
SPOOL DRIVEN BYELECTRIC HAND DRILL
-BENCH
too
• WEST EAST
Figure.2: Schematic cross-section of reactor showingthe method of inserting the copper wire forthe radial flux distribution measurements.
- 21 -
520.7500
8.41
0
•COPPER WIRE IN ALUMINUM TUBE
TOP SHIELD
He SPACE
MODERATOR SURFACE
FLUX DETECTOR THIMBLE
.CALANDRIA FLOOR
Figure 3: Schematic drawing showing method of insertingthe copper wire for the axial flux distributionmeasurement. The elevations above the calandriafloor are in cm.
- 22 -
Figure 5: Top view of counter showing; (1) collimator slot(2) lateral guides(3) vertical guides
I
to
- 24 -
u0)
3Oo
§
O0)COI(001ouo
5-1
- 25 -
PAPERTAPEPUNCH
*COUNTER
1
COUNTER2
i
AUTOMATICCONTROLUNIT
STARTMOTOR
TYPEWRITER
STARTCOUNT
SCANNER1
ti
SCANNER2
Figure 7: Block diagram of counting system.
- 2 6 -
EXFT 1
H-133.4 CM
3) ND CODL.GIMT,H> IflL PIT KL14-1S IIND PQ1B-13
. 10.10-IS
. W1I8-I9
E
.tCDOCC<ai
o.o-SO
Figure 8:
ELEUPTIOINCCri)
Expt. 1 axial flux distribution. The upper andlower rows of values of c, D and E are forKL14-15 and PQ18-19 respectively
1 0
,B
R
.4
,z
0.(1
: EX >T Z (1
?Z4: CM
*
*** 1*
*
**
•
- *
9
UITH EOOLOIN
*
*
*
r
•
**
*<*
. KL11-1S
C
.ISZ44C-
\
0
3 . iconx
E
»Ol .1013
I
-so so ZSO 300 3=0
ELEUOTION(CM)ssa EDO
Pigjure 9: Expt. 2 axial flux distribution. The normalized activitiesat elevations above 370 cm have been multiplied by 50.
ua
1.2
1 .0
.a
. 6
0 . 0
EX
H=
-
W 3 t
381 CT1
*
£•
JS^*.
* i
:
IDU 17
2-8
/
. • / - .
RBSOF
PM BDF
3ERS C
DIN
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35PC)
\ \
*****
\
\
, HL1«1-1S
M PQiB-ia
c
.I1SJ9E-I
\
D
3 .5B06CE
i 7flTnrT
E
•DO .9ESOI z*oo
•
toCD
SCO sso
Figure 10: Expt. 3 axial flux distribution.
ua
0.0 I-50
EX
H=
>T 4 CtHOU 17
133.2 (tri
JH
/
.if
RBSOR3ERSC3
. PQ1B-1!
•01 .SB1I
THERMAL SHIEU3
\iaa ISO ZSO 300 3S0
ELEUOTIDINCCM)
I
coo
Figure 11s Expt. 4 axial flux distribution. The elevation of the top thermal shieldat 520.7 cm is shown. Above 510 cm elevation the normalized activitiesare less than 0.01 and have been multiplied by a factor of 50.
i n
,B
,E
.4
0.0
EX
H=
-SO
'T;S (
»aa..3
**«
/*• -
A
/
s
/A
A
0 a
ou ie
t
i
*A
4.
/A
0 1C
FULL
a is
TflNK,q
A
\%n
m
3SnRC3E
\ .\ % *%
is nau ING 9 3 -
\
3SPC
a roia-ia
c
. ISZZIE-<
\
S .SO4S0E
V
E
•OD .9BZOC
km mm
•*
•
SO SI
E.OD
f*fii
4
A
A
23
A
AAkA
* - \
" . • A Js
d
o
Figure 12: Expt. 5 axial flux distribution
H
0 . 0
• EX
3 .
3T B Cr
«7 ppr
**
*
DU 183
1 BOROr
/*
t
**
PB5DR
V*
3ERS ( 35PCD
\
*
*
N
. KL14-1S
C
.ZZ5Z3C-
"x
0
3 .11151
\
\
Z
•Dl .39101
THERMAL
\
\
SHIELD
\
•
•
I
u>
-so SO 100 ISO ZOO ZSO 3W 3S0
ELEUOTIOIN(CPI)000 ISO SOD SSO GOD
Figure 13: Expt. 6 axial flux distribution.
- 32 -
U 2Q- iLTJ j
01 *
inua:
- B J -uCDain
-O-a
xi
03 7L— D
ggco
£LD
-10-Xu in
• - % ,
• - . » .
' • »
u
82
id
co
-H
VI
+J(0
-H•oX3x
+X
-H
l.Z
1.0
(Ja
0.0
EX
3 .
»T BCNl
374 PPI
t
*•
• ••
)U 19)
1 BORCT
•
FLUX T ILT,flO 3ORBER ;cnRL)
'A
\
\
\
. KLIt-IS
c
\
•
3 .379]
\
C
oi .aeia
\
[•CD
-so SO 100 ISO ZOO ZSO 300 3S0
ELEUPTIONCCn)too «so SOD sso soo
Figure 15: Expt. 8 axial flux distribution
H
1.
1.0
.B
.6
,Z
n.o
EX
3,
=T 9 C
1(95PC
j
**
OU 20
*
*
FLUX
*
TILT.P
.674 P
•v
3S0RDE
'M BOR
\\
V\
S 1 , Z
)(S
V••
V
\
c
.70077E-
0
3 .359<1SE
\
\
E
•oi .iooa
\
E'OI
M a n
*
-SO 100 ISO zoo ZSO 300 3S0
ELEUOTIDMCCM)400 «SQ SOB
I
u>
9S0 SCO
Figure 16: Expt. 9 axial flux distribution.
I.I
i.a
0.0
EIXI
4C
>T 10
3 S P O , ;
•
tt
*
*
INDU z :
'(SPC),
t
*
•
•:
*
) FLUX
3.G74
/
f
TILT ,
PPM D
OSS0R
3RDM
V
•
IERS- 1
t
•
\
1RL5
. KLIO-IS
c
.3SB03C'
0
3 .ISZE3E
\\
C
'01 .SDCO
THERMAL
\
E.DO
SHI
\
-so so too isa zooZSO 300 350
ELEUPTI DISC CH)flOD ISO 500 £50 COO
Figure 17: Expt. 10 axial flux distribution.
1 .
1.0
.B
.6
4
. 1
n,n
EX
3 .
>T 1 1
374 PP
*
*4
*
*
(SOU 2
1 BORD
e
i
*
}
) PDSC
y
:?I3ERS
"V
1(G3PC , 2 , 6 , ;
V
V
•
V
C5PC), 3-5(98. KU1- IS
C
370SIC-
V
X
0
3 . IB500C
\
E
>OI .UBECX
\
\
t.oo
•
I
-so 50 100 ZSO 310 350
ELEUOTIUINCCM)500
Figure 18: Expt. 11 axial flux distribution.
1.0
R
.6
.4
,z
0.0
EX
3.
»T 12
331 PPP
i*
4
•
*
NOU 2^
1 DDR0P1
*
/$
4-
*
*
) FLUX
• *
T ILT , ABSORB
* #
:RG CI PC)
\ .
V.V
. KLI1-I
C
.ZZ3ZIC-
V
"s
0
3 .I33BBC
V
\
c
•oi .saeca
's
\
oca
• M W
•
-SO so too iro zoa Z50 M O 3S0
ELEUOTlOfNCCM)J100 ISO 500 SSO coo
I
Figure 19: Expt. 12 axial flux distribution.
ua
•J.l.Z
'ib. • :•'• • • ' : o
'K'¥\
t .."•ilo
•'••,'(•• Y.y
•?"fe
14
• j 1
on
•»;'::;::'.'ii'i-r'
• ' • ' • ' • • • • ' ' - ' " ) ' , :
! . ; • • • . _ "
•: " ' ;" '
ft;' ' _ ' • •
. : - • " • " : i
BRIBER
l u •:>•.•">'-:,'.;'!
' • • • ! - ' • • ; • T ; • ; - - • ;
. i f , > • • ' " ! : " . •
- : [ ! ' 1 : : • ':'
: ' " • . - . . - • :
':' •. " V
; | ; - | % ; ; : : - :
-".'••: '".'.•; * * i
' ; ' ' : ' ' .•• * i .
•^vi?-'/.;..;
jvi:;./.:.' ;
- • .
i
1 :B0OE
• • - . - . : • ' • • • / • . • • • : . • ; •
, * -0E
*Hi5 f ;•
•:•-!..••• M r . - .
:L:: : ; • /? ; .
TER::3'
3;?PRK :; 30R0M ;i
• v .
!V - '
•»
• • • • • • • ' • ' . ;
h ; , : ' . •..' f-^
:•'••.r:\'\'][
\
\
\
» W.11-IS
;j C
I1 .9I3Z4E-
%
\
a
4 .S3a«E
E
•oo .sattt
\
\
*•.
00
1D0 ISO zoo ZSO 300 3SD
ELEUOTIONCCnD
400
Figure 20: Expt. 13 axial flux distribution.
ua
EX
OB
3T 14
3ORBERS
*
**
ISDU 2*
IC67PC)
*
0-•
%•
*
*
a£*
) BPINK
4.39G
V*
1 HT
PPM B
• **r
?32 CM
DRDM
*
V
. W-11-IS
c
.ICB11E-
V
V,
D
3 -43Z7CE
V
Z
>D0 .37301 E«O0
THERMAL SHIELD
\
*.
s
\
-
•
— . - • *
Figure 21
ELEUflTIONCCm
Expt, 14 axial flux distribution.
5S0 ECU
ua
1.0
. 8
.e
,z
no
EX
RB
»T "15
30RBER
0
•
*
rsou 2
)CG8PC
fi
•*
/
**
1 BRPSK
, 5.D
• • »
1 FUL
dt PPM
.Y IN
30RDM
•V.
•*
V.V
« •
. KLH-IS
C
\
\
a
a .39700C
*
E
•ao .s?°a
t
\•«\
E.cc
•
oI
100 150 zsa 3aa 3
ELEUPTIOrH(Cri)000 4S0 S50 SOP
Figure 22: Expt. 15 axial flux distribution.
ua
EX
PB
T 1G
50RBER!
t
t
t«
}
NOU 2E
ICGBPC)
*•
*
) BRINK
, G.20
*
•
/k
5 1 PN
D p p n
3 2 FU
3ORDIN
.LY IN
>
*
.*
V*.
. KLI4-1S
C
.3G59GE-
V
\
s
\*.
0
4 .I77ZCE
•
E
-CO .S41O
\
\
E>(X)
•
1
SD 100 ISO ZOO ZSO 300 3S0
ELEUOTIONCCn)000 4S0 500 SSO GOO
Figure 23: Expt. 16 axial flux distribution,
1 . "
1.0
.8
h-
^ .G
y
.4
.Z1
0.0
EX
flB
>T 17
50RBER
j
/
r
/
IN0<J 2E
itBBPC
/•
) BRISK
, 7.74
/
S 1
5 P
ON D Z FU
3DRDIN
^ ^
.LY IN
\
BOOSTE
\
R 3C30
C
,.ias«K-
:
4
CM)
0
•I10Z0E
\
• DO
N
c
\
E«PO
X
to
I
-so sn IOD iso zoc 3£0 400 450 500 5*S0 COO
Figure 24: Expt. 17 axial flux distribution.
ua
1 0
.B
4
T
n.o
EX
OB
'T 18
JORBER'
§
NOU 2G
i C71PC
•*
) ONE
D,SOOS
*
coot .PIN
TERS D
.•*
J•
r CIRC
JT, 7 .
JIT HPL
'45 ppr
s."V
F UOIC
BDROh
V
\
:D. KL14-IS
C
.IB44Oe-
V
\
\
D
4 .157ZCC
E
OD .9GGO
\
\
*
V
coo
.
V-5D iCO ZSO 300 3S0
ELEUPTIOfSCCfi)
Figures 25: Expt. 18 axial flux distribution.
1.
1.0
.a
.e
.4
0X1
EXPT 12 OXI
*••
•
3L WIRE 4
•
•
* 1
, 11I
f
•
DjO
, EXPT !Z U
C
.7S5IE-03
HELIUM SPACE V THERMAL SHIELD
V.
PE 1JW4
D C
.133B8E-0I .9BEO0C*IXI
ELEUPTIDMCCri)S50
Figure 26: The upper part of the Expt. 12 axial distribution. Above 490 cmelevation the activities have been multiplied by a factor of 5.
t"5
C U M mm
urucroft un u
i i i f junuun |
EX
•
•
j
'T Z <
224 CM
icw I B
J
• /t
UtTH COOLflN
.-V
r
V
•
S
c
/••••"
1 ,100001
*,
\\^
•oi .am
11':•:-•:•.<
"
COD
•too • •« -«s
Figure 27;
•300 -ZSO -ZCD -ISO -IfXI • !•RPDIUS(CM)
IOD i«i SO 400
Expt, 2 radial flux distribution. The normalized activities atradii greater than 340 cm have been multiplied by 100. Thenegative radii are in the west direction.
I . I
.•
.c
.(
0,0
t
EX
•
t*
' T 3 C
381 CM
100 \7
2.8
SDSOR
PH GOR
3ERS (
T.
35PC)
• . ' *
V
' • ' • " • . .
' • • ' • • • * .
'•: AV •.
"V-.V
s\
. wr a
c
.16O00C-
\
0
\
t
c*oa
•«B -KD -XU -ISO •ISD -IOO -VJ
RPDIUSCCI15101 ISO 100 ISO XII KD
E-
Figure 28: Expt. 3 radial flux distribution.
V-
3 .
H
0.0
•
t
EX
•
•
•
i
t
t
t
;
3T 4 C
193,2 t
i
/
/
€U 17
i
Q135DR
//
A/
3ERSO
•
. '••.• / * '
/ ' " ' • '
1FC)
/
< t
•
•
* ***
'••V
v ••>
~\','••-
. r»*T 4
c
.4Z«|K-
\
'D
3 ,l«Bt
•
\
\
m .naa
i.„•;,-
z*m
-, **,\ A'
|
*0
I
-tU •CD •tea -aso •00 "1CD 'ISO •IOD -SO
RPDIUS(CM)to tOO IK) M» OD MJ
Figure 29: Expt. 4 radial flux distribution.
0.0 *
1I
I- 1
1
rx
H»
•
,'„•
/
t
j
3T 5 !
»9B.3
/
IDU IB
J
TULU
•̂ .
/-•>-• '
TQNK.R
A.
3S0RBt
':/
!S
V
rc 33- 35PC
"• ' ' \
too mwtetDi
CO
I
-IU1 -Ul 0
RQOIUS< O1)aj loo i5D au Mfl mo TO «O
Figure 30: Expt. 5 radial flux distribution.
1.0
a
ts ,—
.(
0.0
II'j \t \ \
r"
•
: •
••
»
;
#»
V
EX
3.
4
t
t
»T. 7 >(
50 PPM
/
I0U IB
QORDN
/
• F'uUX riLT,RI JSORQE
*
! 4C3PC
j \
) ,REST
•A
taspc
•..•' \
i
A
V\A
1 \
\
> OFT?
C 0
i .noa
•
\
\
>
'' IIin
[•01
'« • * .
• • • ' " ' •
V0
-ao -too
HHDIUSCCM)S) 1CD \W tOD HO MO
Figure 31: Expt. 7 radial flux distribution.
I . I
, J)'
.«
0,0
EX
3.
I . - - " : •
\ -
;•
/
*
374 PP
/* •
M 131;
1 00R0
J
FLUX T
/ * *
'"7
IUT,B0
-
iORQER ICMRtJ
~! V v'\v\
. on •
c
.XUGOC*
\
\
\
0
1 .17GBIV
*
*
\\
r
0| ,MGP
I , :•
J
','.•' J'+'j'' ' •* ' •»
1
Oil
o
•«o -<m •ICE -m a so in isi no «ti w si «n
RBDIUStCM) E
Figure 32: Expt. 8 radial flux distribution.
2 ••5
,- i EK
3,
•
<
•
m
t
;
! T : 9 (
U35PC
IOU 20!
.'
J
FTLUX
P C ) , 3
,\
riLT.o
.674 P
35ORGE
'M QOR
!S 1,2
IN
V \
SdiRL
A,
J M
"'-A.A
':•
\
\
, DPI >
C 0
•
\
\
01 .100 t<0>
in
I
• a -no Rnoius:cii)iw rag
eno an
Figure 33: Expt. 9 radial flux distribution.
1.0
t
• • •
o.o
1
rrrx
: EX
no
y
»T 13
JORQTR
J
JNOY 2
iC71PC
J
) BOOS
, 4.0G
TER 3
3 PPCI
"ULLY
30R0N
•V*
X'.
v»
/*•\ ••' v
V J
v
. c*i a
c
•
\
1)
\
c
en .VBD
I
• W -ID
RHDIUStCPI)•a im
Figure 34: Expt. 13 radial flux distribution.
§
• •
II
*• Vvii
•' • • • ' . . ' . ' • • '
• '• *ll
L_ 1
EX
•
*
i
•
J
'T 14
5OR0ER
•>
••
/
(soy z*
; f S ? PC
J
) 0RNK
1.39E
A* > •
1 flT
ppn 0
a> A-*,*
232 CM
3RDN
A A , /' >•& '
v *-
A »>'vt
V
\ \ \
. DM 1
r
t
• .
\
0
i .uca cm
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Figure 35: Expt. 14 radial flux distribution.
H
0.0
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: >
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. •
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c
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•no ••» •4QD -K) • ID -100 -50 0
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Figure 36: Expt. 15 radial flux distribution.
> - • . . •
3 M
A
0.0
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, • "
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• " * • • ' • « .
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-no -i«o -ico in iio ox mE
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Figure 37: Expt. 16 radial flux distribution.
1 ,
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Figure 38: Expt. 17 radial flux; distribution.
1
( T
/ I*, 1.0
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* ; •
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9.0
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r ~'"
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Figure 39: Expt. 19 radial flux distribution.
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