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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

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94

95

94

67

4

5

5

BOOSTER BANK •(cm)

1

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0

0

0

0

0

0

0

0

0

0

0

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330

330

330

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0

0

0

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(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

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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

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- 25 -

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- 2 6 -

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