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ORNL-TM-2823.txt
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ORNL-TM-2823.txt
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—— — — — = — — — = = — e
. ~ CENTRAL RESEARCH LIBRARY
DOCUMENT GOLLEGTION
[ 1 OAK RIDGE NATIONAL LABORATORY
I o operated by
(BN UNION CARBIDE CORPORATION m
| NUCLEAR DIVISION
for the
U.S. ATOMIC ENERGY COMMISSION
| ORNL- TM- 2823
" LIRART ! |
/23
3 445k 0514033 5
|
|
|
|
9
| 4
2
FREQUENCY-RESPONSE TESTING OF THE MOLTEN-SALT REACTOR EXPERIMENT
(Thesis)
R. C. Steffy, Jr.
|
|
[ % Submitted to the Graduate Council of the University of Tennessee in partial fulfillment
i for the degree of Master of Science.
ORNL-TM-2823
Contract No. W-7405-eng-26
REACTOR DIVISION
FREQUENCY-RESPONSE TESTING OF THE
MOLTEN-SALT REACTOR EXPERIMENT
R. C. Steffy, Jr.
Submitted to the Graduate Council of the University of Tennessee in
partial fulfillment for the degree of Master of Science.
MARCH 1970
OAK RIDGE NATIONAL LABORATORY
Oak Ridge, Tennessee
operated by
UNION CARBIDE CORPORATION
for the
U.S. ATOMIC ENERGY COMMISSION
flO(.‘IKHliEDIMAHTN ENERGY RESEARCH LIBRARIES
3 44bE 0514033 5
H
TABLE
LIST OF TABLES + o &« & « & &
LIST OF FIGURES . . . . . .
ACKNOWLEDGEMENTS . . . . .
ABSTRACT . . . . . . . « . .
I.
IT.
ITT.
V.
INTRODUCTION . . . . . .
SYSTEM DESCRIPTION . . .
Physical Description.
Theoretical Predictions
EXPERIMENTAL PROCEIURE .
Test Patterns . . . .
iii
OF CONIENTS
* [} . . . » . - . a *
Pseudorandom binary sequences. . . . .
Pseudorandom ternary sequences . . . . . .
Choice of Pseudorandom sequence . . . .
Signal Generation . .
Rod-jog tests . .
Flux-demand tests.
Rod-demand tests .
Data Acquisition . .
Data Analysis Methods
Computing schemes
Comparison of data
EXPERIMENTAL RESULTS . .
235U Fuel Loading .
Rod-jog tests .
Flux-demand tests,
£33 Fuel Loading . .
Flux-demand tests,
Rod-demand tests .
LIST OF REFERENCES . . . .
APPENDIX . * . * . . . . . .
CONCLUSIONS AND RECOMMENDATIONS., o o o o o o o &
viii
ix
10
13
13
13
18
20
2l
25
26
30
32
3k
34
35
51
51
52
57
6
Qb
103
106
110
iv
LIST OF TABLES
TABLE PAGE
I. Composition of MSRE Fuel Salt . . . . . v +v v v o v o v . L
IT., DNeutronic Characteristics of MSRE with 23 and 235U Fuel
Salt at 1200°F. & v v v v v e e e e e e e e e . 6
IIT. Results of Different Analysis Techniques at 0.016L49 rad/sec
When Applied to Eight Periods of Data . . . . . . . . . Lo
IV. Results of Different Analysis Techniques at 0.4gLTh rad/sec
When Applied to Eight Periods of Data . , . . . . . . . L1
V. Results of Different Analysis Techniques at 0.989L47 rad/sec
When Applied to Eight Periods of Data ., ., . . . . . . . L2
VI. Results of Analysis at a Harmonic Frequency (0,3298 rad/sec) kk
VII. Results of Analysis at a Non-Harmonic Fregquency (O.3h63
rad/SeC). v v v w4 e e e e e e e e e e e e e e e e e L5
VIII. Pertinent Information Related to Each Test Performed for
This Study . . o ¢ & v 0 v v i e e e e e e e e e e 111
LIST OF FIGURES
FIGURE
1. Basic MSRE Flow Diagram . . + « & o o & o o o o o o o o o o
2. Electromechanical Diagram of MSRE Contrcl Rod Drive Train .
3. MSRE Control-Rod Drive Unit Power Transmission Diagram. .
4., Theoretical Frequency Response of Z>°U-Fueled MSRE for
Several Power Levels . . 4 o o o o o o o o o o o o o o
5. Theoretical Frequency Response of £°-Fueled MSRE for
Several Power Levels . .« ¢ & ¢ ¢ o o o o & o o o o s o
6. Example of a Pseudorandom binary sequence, {a) Time Behavior,
(b) Autocorrelation Function, and (c¢) Power Spectrum. . .
T. Example of a Pseudorandom Ternary Sequence, (a) Time
Behavior, (b) Autocorrelation Function, and (c) Power
SPecTrUmM & v v ¢ ¢ ¢ o o 4 o 4 o & o o s & s s s e o s
8. Range Over Which the Power Content of a PRBS or PRIS is
Essentially Flat for Sequences of Various Length and
Bit Times . & v 4 o & o o & o o o o o o o o o o o o o o o
9. Control-Rod Position and Flux for a Typical PRBS Rod-Jog Test,
A Typical PRBS Flux-Demand Test and a Typical PRTS Flux-
Demand Test . . . ... « o e s s s s 4 s o s s s e s s e e
10. Circuitry Used for Generating the Pseudorandom Signals for
the Flux-Demand Tests . . . . + ¢« ¢ v ¢ v ¢ o o o o o« o &
11, Natural Filters for One-Period Analysis and for Eight-
Period Analys is * . . . * . . . . * * » - * o . . . . * 2
PAGE
11
12
15
19
23
27
29
37
vi
FIGURE PAGE
12, Shape of the Analysis Filter Employed by the CPSD Technique
for Various Values of the Damping Factor, ¢ . . . . . . . L8
13. [Frequency-Response Results Obtained by Analyzing a Test Case
Using the CPSD Analysis Scheme with Various Values of the
Damping Factor, £ . « v v ¢ v v v v v v 0 0 o o v o v v Lg
14, Correlation Function and Power Spectrum Results from a
Rod-Jog Test., . & v 4 4 & o v v v v 6 6 v v e o v e e e 53
15. Frequency-Response Results from Rod-Jog Tests . . . . . . . o7
16. Correlation Function and Power Spectrum Results from a Flux-
Demand Test Using a PRBS Test Pattern . . . . . . . . . . 59
17. Frequency-Response Results from a Flux-Demand Test with the
Reactor at 5 Mw with U-235 Fuel . . . . . . . . . . . . . 62
18. Frequency-Response Results from a Flux-Demand Test with the
Reactor at 2 Mw with U-235 Fuel . . . . . . .« . . . . . . 66
19. Correlation Function and Power Spectrum Results from a
Flux-Demand Test Using a PRTS Test Pattern . . . . . . . 67
20. Frequency-Response Results from a Flux-Demand Test Performed
on the £®U-Fueled Reactor .Using a PRTS Test Pattern, . . 70
21, Correlation Function and Power Spectrum Results from a Flux-
Demand Test Using a "Non-Symmetric!" PRTS Test Pattern . . 72
22, Frequency-Response Results from Flux-Demand Tests Performed
on the £2°U-Fueled Reactor Using "Non-Symmetric'" PRTS
Test Patterns . v v v v ¢ o o o o o « .
c e e e e e e 5
vii
FIGURE
23, Examples of the Uncontrolled Neutron Flux During Periods of
8 Mw Power Operation for the 23°U Fuel loading and the
233] Fuel T10adiNg o o o o o o o 0 0 . e s 4 e s 0 e e e s
ol,, Frequency-Response Results from Flux-Demand Tests Using
PRES Test Patterns Performed on the £>%-Fueled Reactor .
25, Frequency-Response Results from Flux-Demand Tests Using
PRTS Test Patterns Performed on the £°AJ-Fueled Reactor .
26. Frequency-Response Results from Rod-Demand Tests Using PRBS
Test Patterns Performed on the £>%U-Fueled Reactor. . . .
27. Frequency-Response Results from Two Periods of a Rod-Demand
Test Using a 242 x L PRTS Test Pattern. . . . . . . . . .
PAGE
78
79
86
95
100
viii
ACKNOWLEDGEMENT
The author wishes to thank Dr. T, W. Kerlin for his guidance in
the direction, for his expert instruction in the theoretical phases of
this study, and for his assistance in the data-interpretation,
Mr, S. J. Ball was responsible for the design of much of the electronic
circuitry used in the testing, was a helpful consultant for all prhases
of the testing, and was very helpful when computer-related problems
occurred. His assistance is gratefully acknowledged. The author wishes
to acknowledge Mr. J. L, Lucius for his help with computer problems.
The cooperation of the entire staff at the MSRE is appreciated,
ix
ABSTRACT
Tests to determine the neutron flux-to-reactivity frequency response
were performed on the Molten Salt Reactor Experiment with the reactor at
various power levels between zero and full power and with the reactor
fueled with a 22U fuel mixture and a 2337 fuel mixture, Test patterns
employed were pseudorandom binary sequences (PRBS) and pseudorandom ter-
nary sequences (PRTS) of various sequence lengths and minimum-pulse-
duration times. 1In some tests reactivity (control-rod position) was
forced to follow the test pattern, and in other tests the neutron flux was
forced to follow the test pattern. The experimental results were analyzed
by several different methods and the results were compared.
The frequency response of the uncontrolled reactor system was found
to be in good agreement with theoretical predictions for both the 2357 ana
233 fuel loadings. There were no indications of response characteristics
that might cause control or safety problems.
The power spectra for the various sequences were flat over the ex-
pected ranges and variations in the sequence specification changed the
power spectra in the expected manner with no anomalous changes. A diagram
is presented which makes specification of the spectral characteristics for
a particular sequence immediate.
For the 75U fuel loading, results of the flux-controlled testing
using PRBS's and PRIS's were adequate, but for the 7%y fuel loading,
additional system noise coupled with equipment limitations caused ex-
cessive scatter in the frequency-response results for both type sequences,
For the ©°2U fueled system, a closed-loop method of positioning the
control rod and use of a PRBS was necessary to obtain acceptable results.
Use of a PRTS with this method of control-rod positioning caused intro-
duction of errors in the indicated control-rod position rendering the test
results unacceptable.
Experimental data were purposely analyzed at non-harmonic frequencies
showing that careful specification of the analysis frequency is necesgary
for meaningful results, 1In data containing a large amount of noise, the
results of analysis of the same data by the different techniques were
found to contain anomalous differences, particularly at the first few har-
monic frequencies, Analysis of the data by the different methods for low-
noise tests gave results which were in excellent agreement.
Keywords: frequency-response testing, MSRE, pseudorandom binary se-
quences, pseudorandom ternary sequences, signal generation, Fourier analysis,
235y 23
’
CHAPTER T
INTRODUCTION
The dynamic response of a nuclear reactor may be characterized by
several methods.l* One of the more useful methods is the determination
of the power-to-reactivity frequency response of the uncontrolled reactor.
Mathematical models are usually formulated which predict the frequency
response before the reactor is in operation., These same models are
frequently used in application of.stability criteria, such as the
Tamiliar Nyquist stability criterion® or determination of the eigen-
values of the system matrix. 2,3 Stability criteria can seldom be
"measured" so the adequacy of the mathematical models must be determined
by some other means. Determination of the adequacy of a model is important
since it is entirely possible that analysis of a mathematical model will
show a reactor to be stable yet the mathematical model may be incapable
of accurately describing the actual response of the system.
One method by which the adequacy of a model may be determined is to
compare the theoretical frequency response with the experimentally de-
termined frequency response. Perhaps more important is that, regardless
of the agreement between the predicted and observed response, once the
*Superscript numbers refer to similarly numbered references in the
IList of References.
experimental frequency response is determined the dynamic response char-
acteristics of the actual system are known and this is the information
of primary interest,
The frequency response of the €357J-fueled Molten-Salt Reactor Experi-
ment (MSRE) was predicted by Ball and Kerlin® and the results of the
initial, experimental, frequency-response tests were reported by the same
authors.® The purpose of the work reported herein was to continue the
experimental tests throughout reactor operation with €357 ag the fissile
material and then to continue the testing program throughout reactor
operation with £33 as the fissile material. Variations were made in
testing signals and testing techniques and the effects of these variations
on the experimentally determined frequency response were noted.
CHAPTER IT
SYSTEM DESCRIPTION
I. PHYSTICAL DESCRIPTION
The MSRE is a liquid-fueled, graphite-moderated, thermal reactor.
The ligquid fuel is composed of the fluorides of uranium, zirconium,
lithium, and beryllium in the proportions shown in Table I. The liquid
in the secondary loop is composed entirely of LiF (70 mole percent) and
BeFo. At full power, the reactor produces about 8 Mw of power which is
dissipated to the atmosphere by an air-cooled radiator through which about
2 x 10° cfm of air is forced. Figure 1 shows the basic flow diagram for
the MSRE,
The basic differences between the dynamic behavior of the MSRE and
most other #%U-fueled reactors arise due to the circulating fuel. The
most apparent effect of the fuel circulation is the birth of delayed neu-
trons in the external loop; indeed, the fuel circulation lowered the
effective fraction of delayed neutrons born in the core from .0067 to
.00kL for the U-235 fuel loading and from .0026 to .0017 for the
U-233 fuel loading.® It requires about 17 sec for fuel leaving the core
region to reenter the core, and at higher powers the effects of fuel salt
reentering the core with a temperature which is representative of the
power level 17 sec earlier also has a pronounced effect on the dynamic
behavior of the neutron flux., Table IT lists certain important facts
about the neutronics of the MSRE, particularly those which affect the dy =
namic response of the reactor.
TABLE T
COMPOSTTION OF MSRE FUEL SALT
2357 Fuel Loading
£33] Fuel Loadingb
(Mole %) (Mole %)
LiF 65 6L.5
BeF o 29.1 30.2
ZrF 5 5.2
UF, 0.9 0.1k
ISOTOPIC URANTUM CONCENTRATIONS
(Atom %) (Atom %)
2337 0 8h.7
234y 0.3 6.9
235U 35 2.5
2363 0.3 0.1
2387 6L, b 5.8
a. Molten-Salt Reactor Program Semiannual Progress
Report, July 31, 1964, USAEC Report ORNL-3708, Oak Ridge
National Laboratory, p. 231, (November 1964).
b. Molten-Salt Reactor Program Semiannual Progress
Report, February 28, 1969, USAEC Report ORNL-4396, Oak Ridge
National Laboratory, p. 130, '
Il REACTOR
|| VESSEL
FUEL
. PUMP
0
|| o0 HEAT EXCHANGER ¢
(o =
X1 o
=\ [1100°F
OVERFLOW
TANK
FREEZE
FLANGE
|
1
F=-T\ 1175°F 1200 gpm
REACTOR CELL
——— — — == ===
| oraIN T 1|
'|TANK |
CELL FREEZE L I
1 VALVE |
I [ [ !
|
] |
| |
| I
SPARE FILL AND FLUSH
FILL AND DRAIN TANK TANK
DRAIN TANK (73 cu ft)
(73 cu ft)
(73 cu tt)
FIGURE 1.
— .
I
[l
1025°F
ORNL-LR-DWG. 56870R{
850 gpm
T
5 I
=)
AlR
200,000 cfm
100°F
Basic MSRE flow diagram,
RADIATOR
COOLANT
COOLANT
PUMP
COOLANTIl
CELL
I
I
I
I
I
I
[
I
I
I
I
300°F
ORAIN TANK
(449 cu ft)
TABLE IT
NEUTRONIC CHARACTERISTICS OF MSRE
WITH 73U and 75U FUEL SALT at 1200°F
£33 Fuel 2357 Fuel
Minimum Critical Uranium Loadinga
. b
Concentration (g U/liter salg) 15.82 33.06d
Total Uranium Inventory (kg) 32.8 207.5
Prompt Neutron Generation Time (sec) L.o x 107% 2.4 x 107
Reactivity Coefficients®
Fuel Salt Temperature (°F)~1 -6.13 x 107° k.1 x 10°°
Graphite Temperature [(°F)~1] -3.23 x 1073 -L.0 x 10°°
Total Temperature [(°F)~1] -9.36 x 107° -8.1 x 107>
Fuel Salt Density +. 4L 0.182
Graphite Density +.54hLY 0.767
Uranium Concentration +.389 0.234
Effective Delayed Neutron Fractions
Fuel Stationary 2.64 x 10773 6.66 x 1073
Fuel Circulating 1.71 x 1072 L.k x 1073
Reactivity Change Due to
Fuel Circulation (% 3k/k) -.093 -0.222
“Fuel not circulating, control rods withdrawn to upper limits.
b
2357 only.
“Rased on 73.2 ft° of fuel salt at 1200°F, in circulating system
and drain tanks.
dBased on a final enrichment of 33% #7°U,
e e eas V) . .
At initial critical concentration.
Where units are shown,
coefficients for variable x are of the form &k/kdx; otherwise, coef-
ficients are of the form xak/ksx.
inghly enriched in the fissionable isotope (91.5% 23U or 93% =7°U).
Source: Haubenreich, P. N. et al,, "MSRE Design and Operations Report,
Part V-A, Safety Analysis of Operation with 237U, " USAEC Report ORNL-TM-
2111, Oak Ridge National Iaboratory, p. 41, (February 1968).
Since the reactivity perturbations for the experimental tests re-
ported herein were introduced by control rod movement, a brief description
of the control mechanism will be given, The reactor is controlled by
three control rods which are positioned in thimbles near the vertical
centerline of the core and are inserted into or withdrawn from the core
as demanded. Normal rod movement (as opposed to a rod scram) is achieved
by activating a single-phase reversible-drive motor. This, in turn,
drives a chain which is attached to a flexible cable that is threaded
with beads of the poison, gadolinium oxide. The cable maneuvers around
two 30° bends in the thimble before reaching the core centerline position.
The three control rods are essentially identical in every respect;
however, during operation, bne of the rods is positioned farther into
the core and is used as a regulating rod., It was through movement of
this rod that reactivity perturbations for the dynamics tests were
introduced,
A schematic diagram of the control-rod drive train is shown in
Figure 2, and a detailed schematic of the drive unit assembly is shown
in Figure 3. These are shown in detalil in order to give the reader a
feel for the complexity of the control rod assembly so that the problems
encountered in trying to determine the exact position of the lower end
of the control rod might be better appreciated.
A complete description of the MSRE physical plant is given in
Reference 7, and a description of the instrumentation is given in
Reference 8.
ORNL-OWG 63 -8334R
INPUT TO SIZE 18 SYNCHRQ CONTROL
TRANSFORMER, PART OF TORQUE
AMPLIFYING ROD POSITION TRANS- —
MITTER IN SHIM REGULATING ROD
LIMIT SWITCH ASSEMBLY
INPUT SIGNAL TO Q-2360 TORQUE
AMPLIFIED ROD POSITION POTEN-
TIOMETER DRIVES IN LOGGER-
COMPUTER ROOM
a— FINE
TO POSITION READOUTS SYNCRO NO.2
IN CONTROL ROOM | — cOARSE 60° PER INCH
OF ROD MOTION
POSITION
POTENTIOMETER
ROO POSITION
INPUT TO SAFETY SYSTEM b
TO SAFETY B
SYSTEM REDUCTION
GEARING
e
FAN SYNCHRO NO.1
MOTOR 5% PER INCH
OF ROD MOTION _
TACH
SERVD
MOTOR
DRIVE
ELECTROMECHANICAL SPROCKET
(m] CLUTCH ,E
REDUCTION \EOUAL RPM o SPROCKET
GEARING [ . 1-TO-¢ GEARS CHAIN
INCLUDES _f 1t
REVERSE
LOCKING
AIR FLOW
OVERRUNNIN
£ ¢ TO COOL ROD
CLUTCH
FLEXIBLE
TUBULAR ROD
SUPPORT-/
v=0.35in/sec I
T X%
POISON ELEMENTS
THIMBLE —
HORIZONTAL
GRAPHITE BARS — GRID PLATE
CORE VESSEL—™
FIGURE 2. Electromechanical diagram of MSRE control rcd drive train.
RATIOS:
POT. ROTATION _ 5°
ORNL-DWG 66-39154a
FINE SYNCHRO ROTATION _ 60°
ROD TRAVEL ~ in.
COARSE_SYNCHRO ROTATION __ 5° 52T, 32op
ROD TRAVEL in, ,
POTENTIOMETER
30T, 320P /c\ SINGLE TURN
ROD TRAVEL — in. 52T, 32DP (/ " 1000
7 T P @ " "
°T 320 @a COARSE" SYNCHRO
26T, 320P 02 A ‘ SIZE 31
26T, 320P &7 Ysi¥<= <57 390p
78T, 32DP “3\‘ , 32D
TS Q‘
SPROCKET, 64T PITCH "FINE" SYNCHRO
CIRCUMFERENCE SIZE 18
4.00 INCHES
— : ELECTROMAGNETIC
SPROCKET CHAIN
proocET , CLUTCH, 32 v dc
3~ in. /, 0.24 omp, ELECTROID CO.
26T, 320P C NO. 2EC-26CC-8-8
/ 54T, 24DP
54T, 24DP
OVERRUNNING CLUTCH
FORMSPRAG TYPE FS/05
WORM, 24DP, SINGLE THREAD
WORM WHEEL
52T, 24DP
u 54T, 24DP
41T, 24DP '
40T, 24DP
14T, 24DP
14T, 240P
SERVO MOTOR, 115 v,
25 2¢ — -
DIEHL cO. MoToR | S0 ¢PS» 25w, 2¢
BASIC ASSEMBLY
NO. FPF 49-91-1
ac TACHOMETER
BLOWER
24T, 2LDP means 24 teeth on diametral pitch of 2k.
FIGURE 3. MSRE control-rod drive unit power transmission diagram.
10
IT. THEORETICAL PREDICTIONS OF FREQUENCY RESPONSE
The mathematical model® which was used to predict the frequency
response of the 235J-fueled MSRE divided the reactor core into 18 fuel
lumps and 9 graphite lumps. The external loop (coolant system and heat
exchanger included) was also modeled using a lumped parameter model.
Results of the initial dynamics tests® were in excellent agreement with
the predictions, so the same basic model was used to predict the response
of the 23j-fueled system,->
Figures 4 and 5 show the theoretical neutron level-to-reactivity
frequency responses for the two fuels. In general, the theoretical curves
will also be shown with the experimental data and are shown here for
comparison purposes.
For the higher power levels, an outstanding feature of these plots
is the dip in the magnitude-ratio curves at about 0.2k rad/sec and
on
’ No-8k ’
the associated "bumps'" in the phase angle. The frequency at which these
occur corresponds to the time required for the fuel to circulate completely
around the primary loop (25 sec) and is caused by the return to the core
region of fuel which has temperature representative of the power level
25 sec earlier. With the £7°U fuel, the dips in the magnitude-ratio
curves were relatively small and were not verified in the initial testing
program,® but for the #37U fuel, the predicted dips were larger and it
was hoped that these could be verified. For a given fuel loading, the mag-
nitude of the dip is a function of the salt mixing> that occurs during the
circulation around the primary system. More mixing causes a less pronounced
dip.
11
ORNL-DWG 69-12243
ZERO POWER T g
I
104
+
30 5 Mw
P
AN
\