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ORNL-TM-1647.txt
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v Y
OAK RIDGE NATIONAL LABORATO
operated by
Rfc g3cc
UNION CARBIDE CORPORATION
NUCLEAR DiVISION LT
for the
U.S. ATOMIC ENERGY COMMISSION
ORNL- TM~- 1647
o
COPY NO. - -+ '3,
DATE - October 13, 1966
GOV~
EXPERIMENTAL DYNAMIC ANALYSIS OF THE MOLTEN-SALT
REACTOR EXPERIMENT*
.
= oUING z
RELEASED FOR ANE: T. W. Kerlin and S. J. Ball
ABSTRACT
Dynamics tests were performed on the Molten-S5Salt Reactor Experiment
(MSRE) for the full range of operating power levels to determine the
power=to-reactivity frequency response. Three types of input disturbances
were used: the pseudo-random binary reactivity input, the pulse reactivity
input, and the step reactivity input.
The frequency response of the uncontrolled reactor system displayed
resonant behavior in which the frequency of oscillation and the damping
increased with increasing power level. Measured periods of natural
oscillation ranged from thirty minutes at 75 KW to two minutes at 7.5 MW.
Thege oscillations were lightly damped at low power, but strongly damped
at higher power.
The measured results generally were in good agreement with predictions.
The observed natural periods of oscillation and the shapes of the measured
frequency response agreed very well with predictions. The absolute amplitude
of the frequency response differed from predictions by a factor that was
approximately constant in any test (though different tests at the same power
level did not have the same bias). This bias difficulty is apparently partly
due to eguipment limitations (sta.ndard MSRE control rods were used) and
partly due to uncertainties in the parameters in the theoretical model.
The mein conclusion is that the system has no operational stability
problems and that the dynamic characteristics are essentially as predicted.
¥ Research sponsored by the U. S. Atomic Energy Commission under
contract with the Union Carbide Corporation.
For presentation at the Winter Meeting of the American Nuclear Society to be
held October 30-November 3%, 1966 in Pittsburgh, Pa.
NOTICE This document contains information of a preliminary nature
and was prepared primarily for internal use at the Oak Ridge Nationel
Laboratery. It is subject to revision or correction and therefore does
not represent a final report.
re LAV EE R BT R g o ceece .o Crape -
[ei8 DOUUMENT B0s T o
IVTRITOOEY S ey gy
MO INVENTCHZ U Bl Dinoeks]
10 THE A.E.C. A;;‘;;&j{g@flaaa THEREIN,
7 ] fo
—
LEGAL NOTICE
This report was prepared as an account of Government sponsored work, Neither the United States,
nor the Commission, nor any person acting on behalf of the Commission:
A. Mokes any warranty or representation, expressed or implied, with respect to the accuracy,
completeness, or usefulness of the information contained in this report, or that the use of
any information, apparatus, method, or process disclosed in this repert may not infringe
privately owned rights; or
B. Assumes any liabilities with respect to the use of, or for damages resulting from the use of
any informotion, epparatus, method, or process disclosed in this report.
As used in the cbove, ‘‘parson acting on behalf of the Commission® includes any employee or
contractor of the Commission, or employse of such contractor, to the extent that such employee
or contractor of the Commission, or employee of such contracter prepares, disseminates, or
provides access to, any information pursuant to his employment or contract with the Commission,
or his employment with such contractor.
IT
TIT
v
Vi
VIiI
ViIT
IX
Appendix A.
Appendix B.
iii
CONTENTS
IntrodUCtiOn.eeseseseessossovrsosasansnons
Description of the MoRE . veeeeecrcssnves
Theoretical PredictionS.esecessssencenssne
A. Description of Mathematical Model...
B. ResulfS.ceerecscensrsstsossscsasesnas
Selection of Experimental MethodsS.seeess
A, Characteristics of the MSRE
RegulatingRod...l'......."‘..l..
B. Test Signals Used in the Experiments
1. Pseudo-random Binary Test..ev...
2. Pulse TestSiseeevrsarcscososncasns
3., Otep TestSeeeeeestesessssorenane
Experimental ProcedureSievseeeeescessess
A. TImplementation of Pseudo-random
Binary TestSeecsaececosonsrecscscns
B. Implementation of Pulse and
StepTests-.ll...ll....l...'l...‘.
Analysis ProcedUreSeceesrsecsssesssasssans
A. Direct Anelysis of PRES TestS.iervaess
B. Indirect Analysis of PRBS TestSeeese
C. Step Response Test Analysis.
®
-
»
L]
*
.
»
.
D. DPulse Response Test AnalysiS.cacesas
ResUltSieeceeessessasasercscanasssonasens
A. Transient RespOnseSesssscessscsssesns
B. Correlation FunctionS.eeessssesssens
C. TFrequency RespONSESeecsecssccssasseass
Interpretation of the Results..cevecevose
ReferenCesSieieenscescsesorenessnssscoscons
Potential Sources of Experimental
Error Due to Equipment Limitations..
The Direct Method for Cross~Power
Spectrlflfl Analysis.a-ooooc-OOOAA‘NOT‘CE
LEGAL
55, OF us¢
letene
rocy, COMPIETEnt pne>
of any spformation, apparaty
rivately owned rlg‘m.s;. ot sttes wh
' [, Assumes any liabili
of mation,
th respect 1©
T
& of any info ppat
* As used in the above,
ployee oF contractor of th:or i\
sm:h employee OF contrac
digseminates, or
Commiss mploymem with &
with the O
ion, OF his &
qes access Oy contractoT.
prov uch
&
O F F F P Hm
10
12
13
13
13
13
13
17
21,
21
21
22
22
32
32
45
L7
1
damages
oyee of guch ©O
y his emplo
port, oF that the use
rt may not iniringe
. repott. _
n*' includes any em
. to the extent that
ntracior prepares,
-1
I. INTRODUCTION
A gseries of experiménts was performed on the Molten Salt Reactor
Experiment (MSRE) to determine the frequency response of the uncontrolled
reactor system. Tests were performed at eight different power levels
ranging from zero to full power. Three different types of input
disturbances were used to obtain the nuclear power to reacti#ity
frequency response: the pseudo-random binary reactivity input, the
pulse reactivity input, and the step reactivity input. Subsequent
sections of this report will give a description of the system, a
review of previously published theoretical predictions, a description
of the testing procedures, and the experimental results.
IT. DESCRIPTION OF THE MSRE
The MSRE is a graphite-moderated, circulating-fuel reactor. The
fuel is a mixture of the molten fluoride salts of uranium, lithium,
beryllium, and zirconium.l The basic flow diagram is shown in Fig.
1. The flows and temperatures shown are nominal values which were
calculated for operation at 10 MW, but heat transfer limitations at
the radiator currently restrict maximum power operation to about
Te5 MW, The molten fuel-bearing salt enters the core matrix at the
bottom and passes up through the core in channels machined out of
unclad, 2-inch graphite blocks. The heat generated in the fuel and
that transferred from the graphite raise the fuel temperature about
50°F. When the system operates at reduced power, the flow rate is
the same as at full power and the temperature rise through the core
is smaller. The heated fuel salt travels to the primary heat exchanger,
where it transfers heat to a non-fueled secondary salt before reentering
the core. The heated secondary salt travels to an air-cooled radiator
before returning to the primary heat exchanger. The design parameters
of major importance from the standpoint of dynamics are shown in Table
1. A detailed description of the MSRE appears in Ref. 1.
|| PRIMARY SALT
|| LIF - 70% 1025° F
Bef, ~ 23% .
“ 2rfy — 5% I LOOF -
Il They — 1% II
I UF, — 1% I SECONDARY SALT
| I LiF — 66%
I A ou - 34% |
Da
ORNL-LR-DWG 56870
REACTOR CELL |
300°F
AIR
167,000 cfm
100°F
SPARE FILL AND FLUSH COOLANT
FILL AND DRAIN TANK TANK DRAIN TANK
DRAIN TANK (68 cu ft) (68 cuft) (40 cu ft)
(68 cu ft)
Fig. 1 MSRE Flow Diagram
-3-
Table 1, MSRE Design Data
Nuclear
Flow
Heat
Temperature coefficient of reactivity
of the fuel, °F-1
Temperature coefficient of reactivity
of the graphite, °F-1
Neutron lifetime, sec.
Total delayed neutron fraction
Reactivity loss due to fuel
circulation, % 8K
K
Flow rate in the primary loop, gpm
Flow rate in the secondary loop, gpnm
Fuel transit time in the core, sec.
Fuel transit time in external primary
loop, sec.
Total secondary loop transit time, sec.
Transfer
Fuel salt heat capacity, MW sec/°F
Graphite heat capacity, MW sec/°F
Heat exchanger heat capacity, MH sec/°F
Bulk graphite ~ fuel salt heat transfer
coefficient, MW/°F
Fuel salt~heat exchanger metal heat
transfer coefficient, MW/°F
Heat exchanger metal, secondary
salt-heat transfer coefficient, MW/°F
Fraction of power generated in the fuel
b7 x 1077
2,6 x lO"'5
L0002k
.00666
~0,.,212
1200
830
8.5
16.7
24 .2
L.2
3.6
0.02
0.36
Q.17
0.93
=l
ITT. THEORETICAL PREDICTIONS
A. Description of Mathematical Model
Throughout the MSRE design effort, a wide variety of mathematical
models was used to predict the dynamic behavior. We will limit our
discussion here to the most up-to-date and detailed model reported,
referred to in Ref. 2 as the "complete'" model. The core fluid flow
and heat transfer eguations were represented by 18 fuel nodes and
9 graphite nodes. The nuclear power distribution and the nuclear
importances for each node were derived from a 2-group neutron diffusion
calculation. The flow rates and heat transfer coefficients for each
node were determined from calculations based on full-scale hydraulic
core mockup tests. The assumed flow mixing characteristics were
verified by transient tests on the mockup.
The neutron kinetic behavior was described by the usual space-
independent equations with six delayed-neutron groups, but with modi-
fications to include the dynamic effects of the circulation of precursors
around the primary loop. The thermal reactivity feedback was computed
by using a weighted nuclear importance for each of the 27 fuel and
graphite nodes. The xenon poisoning reactivity feedback included
iodine production and decay into xenon, xenon decay and burnup, and
xenon absorption into the graphite.
The transport of molten salt in the primary and secondary loop
piping was described by a plug flow model, where heat transfer to the
pipes was included. The primary heat exchanger and the salt-to-air
heat exchanger were each represented by a 50-node model.
B. Results of Theoretical Analysis
Several different methods of solution were used on the various MSRE
dynamics models, including analog and digital computer simulation
(time response), frequency response analysis, and pole configuration
analysis. The frequency response analyses can be directly compared
to the experimental results, since the latter are readily cast in
this form.
Fig. 2 shows the theoretical MSRE inherent frequency response
ORNL-DWG 65-9816
2
10,000
10
o0 2 5 001 2 5 o 2 5 t 2 S 10 2 5 100
FREQUENCY {rodians/sec)
90
80
70
PHASE OF E#%%
60 0
50
40
30
20
PHASE (deg)
o
NO FEEDBACK
-70 ———m ‘
-90
00001 2 5 0001 2 5 oo 2 5 ot 2 5 1 2 5 10
FREQUENCY (radians/sec)
Ffig. 2 MSRE Theoretical Frequency Response
-6
characteristics for normalized neutron level response to reactivity
perturbations at several power levels. It can be seen that the system
becomes more oscillatory at progressively lower frequencies as the
nominal power level decreases, though it is stable for all power levels
of interest. An explanation of the inherent stability characteristics
is given in Ref. 2.
IV. SELECTION OF EXPERIMENTAL METHODS
The selection of the experimental methods for the MSRE dynamics
tests was based on the information required and on the capabilities
of the available equipment. It may be seen from Fig. 2 that the most
significant part of the frequency response is in the range 0.0l to
0.1 radians per second, since the amplitude peaks are in this fregquency
range for the operating power levels of interest. This frequency range
corresponds to long periods of natural oscillation (10 min. to 1 min.).
This emphasis on low frequency results fortunately made it possible
to obtain the important part of the system frequency response using
the standard MSRE control rods to introduce the input reactivity
perturvations. In this section, we will examine the characteristics
of the MSRE regulating rod and the properties of the test signals used.
A, Characteristics of the MSRE Regulating Rod
The MSRE has three control rods, each with an active length of
59.4 inches. One rod is normally designated as the regulating rod and
is used for fine control. The other two rods are shim rods used for
coarse adjustments. The rods are actually flexible, stainless steel
hoses on which are strung gadolinium oxide poison cylinders. The rods
are mounted in thimbles which have two 30° offsetting bends so that
the rods can be centrally located even though there was no room for
the control rod drive assemblies above the central axis of the core.
The maximum rod speed is ~0.5 inches/second.
The three control rods are identical. Figures 3 and 4 show the
control rod and :drive assembly. The position indication for each rod
is obtained from two synchros geared t¢ the rod drive mechanism.
Synchro number 1 is used for coarse position indication and has a
ORNL-LR-DWG 67311
REVERSIBLE DRIVE MOTOR
COOLANT TO DRIVE
ASSEMBLY
COOLING
GAS INLET
COOLING GAS
SOLENOID ACTUATED CONTAINER
RELEASE
' POSITION INDICATOR
:.\ 7z SYNCHRO TRANSMITTER
‘l» FIXED DRIVE SUPPORT AND
|
|
UPPER LIMIT ——{ | 3in. CONTAINMENT TUBE
SWITCH i) —COOLANT TO
orwe uwT b ;'! POISON ELEMENTS
l i i % in.0.0.-3045.5.- FLEXIBLE
LOWER LT ,,.! '. HOSE CABLE
" I!"',"
5“"0 3 h"glth\
ORNE \ <IN
dfl‘ N\ Y 5 * SPRING LOADED ANTIBACKLASH
AN H HEAD AND IDLER GEAR
3 | w0
. % ‘. ‘\T‘
3in. x 2in, ECCENTRIC
REDUCER
16 In. RADIUS x 30° BEND
COOLANT EXHAUST
GUIDE BARS, ———.
4 AT 90°
BEADED POISON ELEMENTS =]
2in. CONTAINMENT THIMBLE —
Fig. 3 Control Rod Drive Assembly
ORNL-LR~-DWG 78808
SYNCHRO NO.2
60° PER INGH OF ROD MOTION ~o=
~s-TAGHOMETER
SERVO POTENTIOMETER
MOTOR SYNGHRO NO. !
5°PER INCH
BRAKE OF ROD MOTION-»
-=— GEAR REDUCER NO.2
ELECTRO-
MAGNETIC
GLUTCH
GEAR
REDUCER NO. {~e=
AIR IN
OVERRUNNING CLUTC
FLEXIBLE
TUBULAR ROD SUPPORT —a=
v=0.5 in/sec
{-TO-1 GEARS
INPUT SPROCKET
SPROCKET GHAIN
REACTOR VESSEL
CELL
Fig. 4 Diagram of Control Rod
POISON ELEMENTS
i He~TEMPERATURE ~ 41400°F
~= POSITION INDICATOR AIR
FLOW RESTRICTOR
\— /= AIR DISCHARGE - RADIAL
PORTS
Drive
~Q=
sensitivity of 5° per inch of rod motion. Synchro number 2 is used
for fine position indication and has a sensitivity of 60° per inch.
The signal from the coarse position synchro is transmitted to a
torque amplifier which drives a single-turn potentiometer feeding
a d-c signal to the MSRE on-line computer.
After the system had operated for some time, it became difficult
to obtain reproducible regulating rod position changes for a given
time of insert or withdraw. This wasg due to the wearing of this
rod and drive assembly caused by frequent use. For the dynamics
tests, one of the rods normally used as a shim rod was used as the
regulating rod. Since it is moved much less frequently than the
normal regulating rod, it had experienced less wear and had much
tighter response characteristics.
There are a number of factors which could adversely affect both
the accurate positioning of the rods and the indications of effective
rod position given by the instruments. BSome of the potential sources
of difficulty are listed in Appendix A.
These observations indicate that the MSRE control rods are hardly
ideally suited for dynamic testing. However, since no provision was
made for special control rods and since the main features of interest
occur at low frequency, the testing program was carried out using
the standard MSRE control rods. Fortunately, the rods performed
far better than expected by their designers, and the final results
were only slightly degraded by equipment problems.
B. Test Signals Used in the Experiments
Three different types of test signals which were used to obtain
the frequency response of the system are described in this section.
(&)
In this test, specially selected periodic series of positive
1) Pseudo-random Binary Test
and negative reactivity pulses called the pseudo-random binary
sequence (PRBS) were introduced. The PRBS has the advantage that its
frequency spectrum consists of a number of harmonics of approximately
equal size. This means that the frequency response may be evaluated
at a large number of frequencies in a single test. The spectrum of
=-10=-
the pseudo-random signal from one of the MSRE tests is shown in
Iig. 5. We note that the signal strength is concentrated in
discrete harmonic frequencies rather than distributed over a
continuous spectrum as in the case of non-periodic (e.g. pulse and
step) signals. This is helpful since it Improves the effective signal-
to-noise ratio at these frequencies.
A PRBS may be generated on-line at the test or may be pre-recorded
in some fashion and played back as a control signal. On-line
generation of the signal was used in these tests (see Section V).
A PRBS is characterized by the number of bits in the sequence and
the bit duration. A bit is defined as the minimum possible pulse
duration in the sequence. All pulses in a PRBS are minimum width or
integral multiples therecof. Numerous sequences may be generated, but
they are restricted to certain specific numbers of bits. In the MSRE,
PRBS tests were run with 19, 63, 127 and 511 bits. If the number
of bits is Z and the bit duration is At, then the PRBS has a period
Z At. The lowest harmonic radian frequency, w5 and the spacing of
the harmoniecs, Aw, is given by ® = Xy = 21t . The PRBS tests which
ZAE
were run and analyzed are shown in Table 2. In each test, the rod
motion was selected to give a reactivity change of 0.02% to 0.03%,
peak to peak. The maximum reactivity perturbation was determined on
the basis of keeping the resulting power level perturbations in the
linear range, i.e. 6N/NO maximum was kept below O.1.
2) Pulse Tests ™)
In theory, it is possible to excite a system with a single
pulse-type disturbance and obtain the frequency resonse by numerically
determining the ratio of the Fourier transform of the output to the
Fourier transform of the input. The frequency response can theoretically
be evaluated at all frequencies since the input has a continuous
frequency spectrum. In practice, the pulse test is often unsatisfactory
because the available signal strength is distributed over all
frequencies, resulting in a small amount of signal around the analysis
frequency and thus poor effective signal to noise ratio.
Input Power Spectrum
0 ORNL DWG. 66-11076
10
_'['[-
Frequency (radians/sec)
Fig. 5 Power Spectrum of the Input PRBS at 0.465 MW
-12-
Several tests using approximately square reactivity pulses of
between 0.01 and 0.02% were employed for the MSRE at zero power.
Tests were carried out both with circulating fuel and with stationary
fuel.
Table 2. Pseudo-Random Binary Sequence Tests
Power Bits in Bit Periodicity of Minimum
Levels (MW) Sequence Duration (sec) +the PRBS (sec) Frequency
(rad/sec)
0 19 6.58 125 .05
0 63 3.35 211 .03
075 511 3.35 1711 0037
L65 511 3.35 1712 0037
1.0 511 3.35 1711 0037
1.0 127 5.02 638 .0098
2.5 511 3.32 1699 .0037
2.5 127 4.97 631 .010
5.0 511 3.33 1701 .0037
540 127 4.97 631 010
6.7 511 3.32 1698 0037
7.5 511 3.33 1701 .0037
7.5 127 4.97 631 010
3) Step Tests!?)
If the output eventually levels off to some constant value
after a step disturbance, the frequency response may be obtained by
a modified Fourier analysis of the output and the input. As with the
pulse tests, the step input has a continuous spectrum, but is hampered
by a low effective signal-to-noise ratio at any analysis frequency.
Step tests were used at power levels where the temperature feedback
was adequate to cause the power to level off near the original power
after the reactivity change. These tests used a reactivity perturbation
of 0.01 to 0.02%. Step tests were done at 2.5, 5.0, 6.7, and 7.5 MW.
-13-
V. EXPERTMENTAL PROCEDURES
A. Implementation of Pseudo-random Binary Tests
The pseudo-random binary reactivity sequence required a very
precisely controlled series of regulating rod insertions and with-
drawals. Since the frequency range of interest was from about 0.002
to 1.0 radian/sec., the rod jogger was designed so that sequence with
a bit time of 3 to 5 seconds could be run for as long as 1 hour. The
rod jogger system, which required no special-purpose hardware,
consisted of a hybrid computer controller shown schematically in Fig.
6. The portable EAT-TR-10 analog computer was used to control the
bit time and the rod drive motor "on" times for the insert and withdraw
commands. The MSRE digital computer was programmed to control the
(3)
The number of bits in the sequence could be varied over a range between
3 and 33,554,431 bits.
The rod jogger system performed extremely well, as it was able to
sequencing of the pulse train by means of a shift-register algorithm.
position the rod with an indicated positioning accuracy of about
+0,01 in. (corresponding to +0.0005% 8k/k) out of 1/2 in. peak-to-peak
rod travel for over a 500 insert-withdraw operations. A typical PRBS
rod position signal is shown in Fig. 7 and a typical record of neutron
flux changes during a PRBS test is shown in Fig. 8.
The analog computer was also used to amplify and filter the rod-
position and power-level signals prior to digitizing. Throughout the
dynamic tests the MSRE computer was used in the fast scan mode to
digitize and store the data on magnetic tape. Each variable was
sampled at the rate of 4 per second.
B. Implementation of Pulse and Step Tests
The same set up as described in (A) was used for the pulse and
step tests with the PRBS generator omitted.
VI. ANALYSIS PROCEDURES
A. Direct Analysis of PRBS Tests
The "direct" method of analysis uses a digital computer simulation
of an analog filtering technique for obtaining cross-power spectral
(6)
density functions. A bplock diagram of the analyzer is shown 1n
INSERT
ROD-POSITION
:/ SIGNAL