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Conf-660206-2 .
NEUTRON FLUCTUATION MEASUREMENTS AT OAK RIDGE NATIONAL LABORATORY
D. N. Fry D. P. Roux C. W. Rickers S. E. Stephenson
S. H. Hanauera J. R. Trinkod
Oak Ridge Netional Laboratory
Oak Ridge, Tennessee ..
SEB 280
RELEASED FOR ANNOUNCEMENT,
IN AUCHBAR SCL.DNOS ABSTRACTS.
INTRODUCTION
Since our last report on neutron power-spectral-density (NPDS) measure-
ments at CRNL, we have performed experiments at three reactors to determine
the delayed neutron loss in a circulating-fuel reactor, to evaluate a core
for a high-flux reactor, and to measure the NPSD during a boiling experiment
at the Oak Ridge Research Reactor (ORR). Currently, we are evaluating the
use of a counting-rate circuit to measure subcritical reactivity, and pre-
liminary results are promising.'
MEASURE OF B IN A CIRCULATING -FUEL REACTOR
The effective delayed-neutron fraction Be is less in a circulating-fuel
reactor, because the precursors decay while the fuel is outside the core.
NPSD measurements made with the Molten Salt Reactor Experiment (MSRE) at zero.
power are used to determine the difference in B. When the fuel is circulating
and not circulating in the primary loop.
... The MSRE? 18 a single-region, unclad, graphite-moderated fluid-fuel
reactor with a design heat-generation rate of 10 Mw. The reactor heat is
transferred from the circulating fuel to a similar coolant salt and 1s
dissipated to the atmosphere. The circulating fuel is in the core approxi-
mately 9 sec and outside the core in the external loop about 16 sec.
PResearch sponsored by the U. S. Atomic Energy Commission under contract
with the Union Carbide Corporation.
Present address: Dept. of Physics, Abion College, Albion, Michigan. :*
summer research participant from the University of Arkansas, Fayetteville,
Arkansas.
University of Tennessee, Knoxville, Tennessee. .
1.
A Reuter-Stokes, type 81A lonization chamber filled with 2 atm BF3,
which has a neutron sensitivity of 1.3 x 10-13 amp/nv was installed in a :
vertical penetration of the thermal shield at the midplane of the core. With
the reactor at a power of 10w, the current fluctuations from the chamber were
amplified. by a low-noise wide-band ac amplifier and recorded for 1 hour on
magnetic tape using a frequency-modulated tape recorder. The recorded sig-
nals for each reactor condition (fuel circulating and not circulating) were
analyzed using a multichanral spectral density analyzer. (See ref 1 for a
detailed description of the equipment, analysis procedure, and data reduction.).
A digital least-squares program,3 was used to fit the parameters of a theore-
tical model to the observed spectra. The model assumes an infinite homogeneous
one-speed reactor with one group of delayed neutrons. A constant was added
to the spectral density predicted by the theoretical model to account for the
detection-noise component of the observed NPSD.
Figure I shows the results of the MSRE measurements. (In this and all
other figures the standard deviation for a data polnt is smaller than the
size of the point representing the data, unless otherwise shown.). In fitting
the model to the measured spectra, the neutron generation time a was held con-
stant at the design value and the least-squares program was allowed to fit
Ber the one-group effective delayed neutron decay constant a, the detection
noise component Q, and the overall amplitude of the reactor neutron noise.
Figure la illustrates the effect of fuel circulation on the NPSD. The decrease
in B. due to fuel circulation results in an increased reactor gain, and thus,
the NPSD is greater in the frequency range where delayed neutrons affect
the reactor dynamics.
. Figures Ib and lc show the measured spectra with the detection noise
component Q, as determined by the core, subtracted, and also show the least-
squares fit of the data to the theoretical model. The standard deviation of
higher frequency data points 18 due to the subtraction of one number from
.
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another of nearly equal magnitude. The leas't-squares fit indicates that B.
18 Lucreased by a factor of 1.58 0.22 whea circulation of the fuel is
stopped. Independent measurements* (using control-rod calibration) yielded
a corresponding increase of 1.47. This agreement is good, considering that ..
the detection efficiency was low as made evident by the small ratio of reactor-
correlated neutron fluctuations to the detection noise Q.
SUBCRITICAL REACTIVTY MEASUREMENIS IN A HIGH-FLUX ISOTOPE REACTOR (HFIR) CORE
NPSD measurements were made od the CRML Critical Facility on the first
HFIR core. Such measurements will be made routinely to evaluate the worth
of each HFIR core prior to installation in the reactor. Once this informa-
tion is known, any changes in the observed shutdowa margin of the HFIR when
the core is installed in the reactor can be attributed to control-rod and
beryllium-reflector buruup.
The FFIRS is a beryilium-reflected, lightwater cooled and moderated,
flux-trap type reactor which utilizes highly enriched 2350 aluminum-clad
fuel. The design power level is 100 Mw. The core, a 2-ft-high, 17-in. OD
cylinder, has a 5-in. diameter hole in the center. The control plates, in
the form of two thin poison-bearing concentric cylinders, are located in an
annular region between the outer fuel element and the beryllium reflector.
The control rods and inner layer of the beryllium reflector will be replaced
after 6 to 12 months of operation because of burnup.
For the NPSD measurements, the HFIR core was surrounded by an infinite.
reflector of water in a tank at the critical facility. Since the core is
Bubcritical by almost 5 dollars when surrounded by a water reflector, addi-
tional fuel was placed in the center hole to make the core critical. The
fluctuating signals from a Reuter-Stokes, type 81A jonization chamber placed .
i
1
adjacent to the core were recorded on magnetic tape and analyzed in the same
manner as described for the MSRE measurements. The core was poisoned for
the subcritical measurements by placing stainless. steel strips containing
boron between the fuel plates. These strips were calibrated using period
til
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The measured spectra and the least-squares fit of the theoretical model
(the same as used in the MSRE measurements) to the data are shown in Figure 2.
The neutron generation time was obtained from the critical data and then
assumed to be constant for the subcritical runs. The results of the critical
and subcritical measurements (Table 1) show that a 10-cent change in subcriti-
cal reactivity in the vicinity of minus 2 dollars 18 observable. With this
sort of resolution we hope to detect changes in the worth of successive FEIR
cores before they are placed in the reactor. When sufficient reference data
are obtained to determine the basic differences in core worth, the burmup
of the control plates and the beryllium reflector can be deduced from NPSD
measurements made after the core is installed in the reactor. Measurements
made at the reactor site with production core No. 1 in the reactor are cur-
rently being evaluated. .
.
MEASUREMENTS AT THE ORR DURING A BOILING TEST
4
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.
To test the merit of a suggestion that NPSD measurements might be used
to detect the onset of mucleate boiling in the ORR, neutron-induced fluctus.
tions in an ion chamber during a boiling test? at the ORR were analysed to
determine if any noise related to bolling could be detected. The spectra
obtained from this analysis were compared with similar spectra measured under
nonboiling conditions.
The CRR$ 18 a light-water moderated and cooled reactor using enriched
uranium fuel. It 18 designed for power levels up to 30 MW at a coolant
flow rate of 18,000 sm. Boiling was produced in the reactor by reducing

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the coolant flow through a single fuel element by means of an orifice
.inserted in the coolant Inlet to the fuel element. The output signals of
a boron-coated chamber at several power levels were tape recorded, and the
l'ecorded signals were analyzed using the multichannel spectral-density analyzer.
Thermodynamic calculations had predicted that the water in the orificed
fuel element would boil at a reactor power of 6.4 Mw with a total coolant:
flow of 10,300 grm through the core. However, at 6.2 Mw, neutron density
oscillations of about 2 cycles/sec (characterizing bulk boiling) occurred.
But, since the purpose of neutron fluctuation measurerents in this case was
to detect boiling before it reached the bulk-boilling stage, data were taken
at 3, 4.75 and 5.75 Mw to determine if the neutron spectra revealed any
evidence of nucleate bolling.
The spectra obtained from these measurements (Figure 3) were normalized
to the lon-chamber dc curreat, which in effect is a normalization to reactor
power. The obvious feature of the spectra is the peak at 11 cycles/sec.
The data also show that the measured NPSD Increases roughly as the square of
reactor power at frequencies below 14 cycles/sec. However, hefore we made ·
any conclusions concerning these spectra and nucleate boiling, we took addi-
tional data under normal operating conditions with no orificed fuel element. :.
Figure 4 shows. The results of these measurements, also normalized to the dc
chamber current. The spectra of Figure 4 have the same characteristic peaks
at 11 cycles/sec and dependence on the square of reactor power in the lower
frequency rangè as noted previously for the boiling-test spectra. In this
second series of tests, the chamber was placed closer to the core, thus
increasing the detection efficiency. This change accounts for part of the
increased ratio of reactor-related noise to the detection noise component of : :
the spectra in Figwe h. Further measurements made at a reactor power of
4.8 Mw at different coolant flow rates yielded the spectra shown in Figure 5. .
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These results show that the amplitude and shape of the spectra are extremely
dependent on the coolant flow. This dependency is the wajor reason for the
difference in boiling test results and the spectra of Figure 4.
We therefore conclude that if nucleate boiling indeed occurred, its
presence was not observable in any of the spectra obtained during the boiling
test. In reactors of this type the NPSD is apparently strongly dependent
on coolant flow so that even if boiling occurred at lower frequencies, it's
effect on the NPSD would be masked by coolant-flow-induced neutron fluctuations.
Furthermore, we believe that the inability to cbserve nucleate boiling in
reactors using neutron 'fluctuation measurements is due partly to the low gain
of the system at the relatively high frequencies that are characteristic of
nucleate boiling noise. In other nucleate boiling experiments using acoustic
detection methods, signaj.s were detected at about 1 kc. 20 For frequencies
around 1 ko the power-to-reactivity gaia o? the ARR 18 down two orders of"
magnitude from the gain in the range of i to 10 cycles/sec. Experiments are
currently being planned in which acoustic noise from reactors will be analyzed
in an attempt to detect nucleate boiling,
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NPSD MEASUREMENTS USING PULSE-TYPE NEUTRON DETECTORS
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The use of neutron fluctuations to measure reactor parameters is well
established. 2, 11 However, the potential advantages of such measuring methods
have not been realized in practice, partly because of the high gamma-ray
intensities associated with shut-dowa reactors after a period of operation
at high power. To overcome this obstacle to the practical use of shut-dowa
reactivity fluctuation measurements, we investigated the use of pulse-type
neutron detectors ia place of integrating current-type detectors used in
most of the previous experiments. The advantage of detecting Individual
pulses 18 that we can discriminate between neutron-induced signals and smaller
gamma-rey-induced signals, and the gamma-ray signals can be eliminate
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measurement can then be based wholly on the neutron-induced portion of ;
the signal from the detector,
We performed a preliminary investigation at the Pool Critical Assembly
(PCA) in which measurements were made on a cold, clean core using a bit :::
counter (Reuter-Stokes type 425). The pulses from the detector were ampli-
fied, clipped, and applied to the input of a pulse-height selector (PHS).
Output pulses from the PHS were shaped and sent to a linear counting-rate
circuit having a time constant of 10- sec. The fluctuating portion of the
output voltage of the counting-rate circuit was analyzed using a multi-
channel spectrum analyzer.The results of these pulse detector tests were
compared with simultaneous measurements made using an integrating current-
type detector (Reuter-Stokes type 81A).
Figure 6 shows the spectra obtained using tile pulse-type detector and
the results of a least-squares fit of the theoretical model described pre-
viously for the MSRE experiment. Since, as seen in Table 2, the results
of the pulse measurements agree with those obtained using the current detector,
we are planning another experiment in which a boron-coated proportional
counter with higher nextron sensitivity will be used to investigate further
this method of measuring shut-down reactivity in the presence of high-intensity
gamma radiation. i . .
VA
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-
ACKNOWLEDGEMENTS
-.
..-
The authors express their appreciation to J. T. De Lorenzo for his
valuable technical assistance and to G. C. Juerrant and C. B. Stokes for
assistance in performing the experiments and analyzing the data.
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LEGAL NOTICE
The roport was prepared u w soort al Government sponsored work. Med that the United
Statoo, nor the Commission, nos many pordou nottung an domat o the Commissons
A. Makes my warranty or representation, proceed or implied, wek roopnet to the noor-
rhoy, complotonown, or watalions of the taformation contained a while report, or that there were
of any information, apparatin, method, or prooms direloond to this report may not intringo
privately owned that they are
.::D. Anminns may labuities with rotpoot to the wood, or for damaguerol thung from the
une of any Indorniation, apparate, wethod, or prono del polowed to the reports
i AS Mond to the above, perenni notte an honell at the Commission is toldma muy u
proyna or continent of the Commutation, or uplovus or more contrnotor, to the extent that
mol amphorus or contractor this Commission, of employs of male contractor preparos,
dienomination, or provide soon to any mormation permit to Me employment or contract
with the Commission, og han employnion which made contractor.

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TABLE 1. RESULAS OF NEUTRON FLUCTUATION MEASUREMENTS
:... ON. HFIR PRODUCTION CORE NO. 1
-
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.
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CRITICAL CORE
NB = (0.547 6 0.012) * 10-2 sec
SUECRITICAL CORE
(dollars)
Measured pi
(dollars)
,
.
.
-1.06 + 0.20
-2.13 $ 0.2
-2.23 $ 0.2
-0.934 + 0.044
-2.83 0.08
-.95 $ 0.10
*Predicted p based on calibrated boron-stainless steel
poison strips
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TABLE 2. COMPARISON OF PULSE TYPE AND CURRENT-TYPE DETECTOR MEASUREMENTS
PULSE
CURRENT
73.3 $ 9.5
64.3 + 2.3
Neutron generation time (reactor
c ritical), wobec
Subcritical reactivity, dollars :
. 2.26 0.20
.-2.47 6 0.17
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References
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.
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.. .
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.
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1. C. W. Ricker et al., Measurement of Reactor Fluctuation Spectra and
. Subcritical Reactivity, ORNL-IM-1066 (April 1965).
2. R. C. Robertson, MSRE Design and Operations Rerort: Part 1. Description
of Reactor, Design, ARNL-TM-728 (January 1965),
3. W. R. Busing and H. A. Levy, ORGIS. A General Fortran Least Squares
Program, ORNL-TM-271 (August 1962).
4., B. E. Prince, Molten-Salt Reactor Program Semiannual Progress Report
: Lor Period Ending August 31, 1965, ORNL-3872, p 75. (December 1965).
·5. F. T. Binford and E. N. Cramer, The High-Flux Isotope Reactor, ORN-3572
(May 1964).
6. A. I. Colombo and F. T. Binford, The Detection of Boiling in a water-
:: Cooled Nuclear Reactor, ORNL-TM-274 (August 1962). :
7. W. H. Tabor and S. S. Hurt, III, Jak Ridge Research Reactor Quarterly
Report, ORNL-TM-1290, p 30 (October 1965).
8. T. E. Cole and J. P. Gill, The Oak Ridge National Laboratory Research
:: Reactor (QRR), ORNL-2240 (January 1957).“.
9. S. E. Stephenson et al., Neutron Fluctuation Spectra in the Oak Ridge
Research Reactor, ORNL-IM-1401 (February 1966).
10. L. C. James, "Experiments on Noise as an Aid to Reactor and Plant Operation,
Nucl. Engr. 10. (104), 18-22 (1965). .
11. J. A. Thie, Reactor Noise, Roman' and Littlefield, Inc., New York, 1963.
*
.
29
*
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List of Figures
Fig. 1 - Measured neutron power spectra normalized to dc lon-chamber
current for the MSRE at a power of 20 watts.
Fig. la - Spectra before subtraction of detection noise.
Fig. 1b - Spectrum minus detection noise with fuel circulating.
Fig. lc - Spectrum minus detection noise with fuel stagnant.
Fig. 2 - HFIR core spectra normalized to dc, current in the ion chamber.
Fig. 3 - Mautron power spectra of the CRR during the boiling test. . . .
Fig. 4 - Neutron power spectra of the CRR under normal operating conditions.
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