U.S. patent number RE28,477 [Application Number 05/335,165] was granted by the patent office on 1975-07-08 for method and apparatus for measuring neutron characteristics of a material surrounding a well bore.
This patent grant is currently assigned to Schlumberger Technology Corporation. Invention is credited to William B. Nelligan.
United States Patent |
RE28,477 |
Nelligan |
July 8, 1975 |
**Please see images for:
( Certificate of Correction ) ** |
Method and apparatus for measuring neutron characteristics of a
material surrounding a well bore
Abstract
In the particular embodiments of the invention described herein,
the formation surrounding a well bore is irradiated with a burst of
neutrons and the neutron concentration is observed during selected
time intervals after irradiation to determine the thermal neutron
decay time characterizing the formation. In one embodiment, the
neutron concentration is observed during a first interval one decay
time long and during a second and subsequent interval two decay
times long which starts immediately after the first interval. In
another embodiment the two intervals are spaced by one decay
time.
Inventors: |
Nelligan; William B. (Danbury,
CT) |
Assignee: |
Schlumberger Technology
Corporation (New York, NY)
|
Family
ID: |
26989578 |
Appl.
No.: |
05/335,165 |
Filed: |
February 23, 1973 |
Related U.S. Patent Documents
|
|
|
|
|
|
|
Application
Number |
Filing Date |
Patent Number |
Issue Date |
|
Reissue of: |
592795 |
Nov 8, 1966 |
03566116 |
Feb 23, 1971 |
|
|
Current U.S.
Class: |
250/262;
250/269.8 |
Current CPC
Class: |
G01V
5/102 (20130101); G01V 5/108 (20130101) |
Current International
Class: |
G01V
5/10 (20060101); G01V 5/00 (20060101); G01t
001/16 () |
Field of
Search: |
;250/261,262,269,270
;324/61P |
References Cited
[Referenced By]
U.S. Patent Documents
Primary Examiner: Lawrence; James W.
Assistant Examiner: Willis; Davis L.
Attorney, Agent or Firm: Brumbaugh, Graves, Donohue &
Raymond
Claims
I claim:
1. A method for logging a characteristic of an unknown material
comprising irradiating the material with neutrons during at least
two spaced irradiation intervals, detecting indications of the
neutron concentration in the material during first and second
periods, respectively, after commencement of the corresponding
irradiation interval, determining a neutron characteristic of the
material from the detected indications occurring during at least
one measurement interval during the respective periods, the time of
occurrence of at least one measurement interval during the second
period being variable, and controlling automatically the variable
time of at least one measurement interval during the second period
in accordance with the neutron characteristic determined from the
indications detected during the first period in the same logging
run.
2. A method according to claim 1 including the steps of detecting
indications of the thermal neutron concenetration in the material
during the first and second periods, determining the thermal
neutron decay time of the material from indications detected during
the first period, and controlling the time of at least one
measurement interval during the second period in a manner tending
to optimize the measurement of neutron concentration indications
for determination of the thermal neutron decay time.
3. A method according to claim .[.3.]. .Iadd.1 .Iaddend.including
the steps of detecting indications of the concentration in the
material of neutrons having greater than thermal energy during the
first and second periods, determining the neutron slowing down time
from indications detected during the first period, and controlling
the time of at least one measurement interval during the second
period so as to optimize the measurement of neutron concentration
indications for determination of the neutron slowing down time.
4. A method for logging a characteristic of an unknown material
comprising irradiating the material with neutrons during at least
two spaced irradiation intervals, detecting indications of the
neutron concentration in the material during first and second
periods, respectively, after commencement of the corresponding
irradiation interval, measuring the detected indications at least
during a first measurement interval occurring at first times during
the respective periods and during a second measurement interval
occurring at second times during the respective periods, at least
one of the second irradiation interval, the first and second times
in the second period, and the first and second measurement
intervals during the second period being variable, determining a
neutron characteristic of the material from the measurements made
during the first and second measurement intervals in the first
period, and controlling automatically the duration of at least one
of the second irradiation interval, the first and second times in
the second period, and the first and second measurement intervals
in the second period, in accordance with the neutron characteristic
of the material determined from the measurements made during the
first period of the same logging run.
5. A method according to claim 4 wherein the duration of the first
time in the second period is controlled in accordance with the
neutron characteristic determined from the measurements made during
the first period.
6. A method according to claim 4 wherein the duration of the second
time in the second period is controlled in accordance with the
neutron characteristic determined from the measurements made during
the first period.
7. A method according to claim 4 wherein the duration of the first
measurement interval in the second period is controlled in
accordance with the neutron characteristic determined from the
measurements made during the first period.
8. A method according to claim 4 wherein the duration of the second
measurement interval in the second period is controlled in
accordance with the neutron characteristic determined from the
measurements made during the first period.
9. A method according to claim 4 wherein the duration of the second
irradiation interval in the second period is controlled in
accordance with the neutron characteristic determined from the
measurements made during the first period.
10. A method according to claim 4 wherein the durations of the
first and second selected times in the second period are controlled
in accordance with the neutron characteristic determined from the
measurements made during the first period.
11. A method according to claim 4 wherein the durations of the
first and second measurement intervals in the second period are
controlled in accordance with the neutron characteristic determined
from the measurements made during the first period.
12. A method according to claim 4 wherein the neutron
characteristic of the material is determined by comparing the
measurement made during the first measurement interval of the first
period with the measurement made during the second measurement
interval of the first period.
13. A method according to claim 4 wherein the first measurement
interval has a duration approximately equal to a neutron
characteristic time constant of the material and the second
measurement interval has a duration approximately equal to twice
the same neutron characteristic time constant of the material.
14. A method according to claim 4 wherein the first and second
measurement intervals are substantially contiguous.
15. A method according to claim 4 wherein the first and second
measurement intervals are spaced by an interval approximately equal
to a neutron characteristic time constant of the material.
16. A method according to claim 4 wherein the first and second
measurement intervals are within a time period extending from about
twice the characteristic time constant of the material after the
corresponding irradiation interval to about six times the neutron
characteristic time constant of the material after the
corresponding irradiation interval.
17. A method according to claim 4 wherein the duration of the
irradiation intervals is approximately equal to twice the neutron
characteristic time constant of the material.
18. A method for logging a characteristic of an unknown material
comprising irradiating the material with neutrons during at least
two spaced irradiation intervals, detecting indications of the
neutron concentration in the material during first and second
periods, respectively, after commencement of the corresponding
irradiation interval, measuring the detected indications at least
during a first measurement interval occurring at first times during
the respective periods and during a second measurement interval
occurring at second times during the respective periods, at least
one of the second irradiation interval, the first and second times
in the second period, and the first and second measurement
intervals during the second period being variable, determining a
neutron characteristic of the material from the measurements made
during the first and second measurement intervals in the first
period, controlling automatically the duration of at least one of
the second irradiation interval, the first and second times in the
second period, and the first and second measurement intervals in
the second period, in accordance with the neutron characteristic of
the material determined from the measurements made during the first
period of the same logging run, measuring detected indications
representative of background radiation during a third measurement
interval occurring at third times during the first and second
periods, respectively, and subtracting the measurement obtained
during the third measurement interval from the measurements
obtained during the first and second measurement intervals in the
same logging run in determining the neutron characteristic.
19. A method for logging a characteristic of an unknown material
comprising irradiating the material with neutrons during at least
two spaced irradiation intervals, detecting indications of the
neutron concentration in the material during first and second
periods, respectively, after commencement of the corresponding
irradiation interval, measuring the detected indications at least
during a first measurement interval occurring at first times during
the respective periods and during a second measurement interval
occurring at second times during the respective periods, at least
one of the second irradiation interval, the first and second times
in the second period, and the first and second measurement
intervals during the second period being variable, determining a
neutron characteristic of the material from the measurements made
during the first and second measurement intervals in the first
period, controlling automatically the duration of at least one of
the second irradiation interval, the first and second times in the
second period, and the first and second measurement intervals in
the second period, in accordance with the neutron characteristic of
the material determined from the measurements made during the first
period of the same logging run, measuring detected indications
representative of background radiation during a third measurement
interval occurring at third times during the first and second
periods, respectively, subtracting the measurement obtained during
the third measurement interval from the measurements obtained
during the first and second measurement intervals in the same
logging run in determining the neutron characteristic, and
controlling automatically the third time in the second period in
accordance with the neutron characteristic determined from the
measurements made during the first period of the same logging
run.
20. A method for logging a characteristic of an unknown material
comprising irradiating the material with neutrons during at least
two spaced irradiation intervals, measuring the rate of change of
neutron concentration in the material during corresponding first
and second measuring intervals occurring after commencement of the
respective irradiation intervals, the time of occurrence of the
second measuring interval being variable, and controlling
automatically the time of the second measuring interval in
accordance with a neutron characteristic of the material determined
from a measurement made during the first measuring interval in the
same logging run.
21. Apparatus for logging a characteristic of an unknown material
based upon successive detected indications of the neutron
concentration in the material following successive irradiations of
the material with neutrons during the same logging run comprising
conductor means for receiving signals representing the detected
indications and synchronizing signals related to the time of
initiation of each neutron irradiation, at least one variable gate
means responsive to the synchronizing signals and the neutron
concentration indication signals for transmitting neutron
concentration indication signals during at least one corresponding
measurement interval occurring at at least one measurement time
after receipt of a synchronizing signal, comparing means responsive
to the neutron concentration indication signals transmitted by the
gate means to produce a comparison signal related to the neutron
concentration in the material at the measurement time, and control
means responsive to the comparison signal to produce a control
signal for controlling automatically the operation of the gate
means, wherein the control means includes variable frequency
oscillator means responsive to the comparison signal to produce a
control signal having a controlled frequency.
22. Apparatus for logging a characteristic of an unknown material
based upon successive detected indications of the neutron
concentration in the material following successive irradiations of
the material with neutrons during the same logging run comprising
conductor means for receiving signals representing the detected
indications and synchronizing signals related to the time of
initiation of each neutron irradiation, at least one variable gate
means responsive to the synchronizing signals and the neutron
concentration indication signals, for transmitting neutron
concentration indication signals during at least one corresponding
measurement interval occurring at at least one measurement time
after receipt of a synchronizing signal, comparing means responsive
to the neutron concentration indication signals transmitted by the
gate means to produce a comparison signal related to the neutron
concentration in the material at the measurement time, and control
means responsive to the comparison signal to produce a control
signal for controlling automatically the operation of the gate
means.
23. Apparatus according to claim 22 including second gate means
responsive to the synchronizing signals and the neutron
concentration signals for transmitting neutron concentration
indication signals during a second measurement interval occurring
at a second measurement time after receipt of a synchronizing
signal.
24. Apparatus according to claim 23 wherein the control means
includes means for producing a control signal for controlling the
selected measurement time of at least one gate means.
25. Apparatus according to claim 23 wherein the control means
includes means for producing a control signal for controlling the
measurement interval of at least one gate means.
26. Apparatus according to claim 23 wherein the control means
includes means for producing control signals for controlling the
selected measurement time and the measurement intervals of both
gate means.
27. Apparatus according to claim 22 including output means
responsive to the control means for providing indications of a
characteristic of the unknown material.
28. Apparatus for logging a characteristic of an unknown material
comprising neutron source means for irradiating the material with
neutrons for an irradiation interval upon receipt of a control
signal, at least one of the time and duration of the irradiation
interval being variable, detector means for producing indications
of the neutron concentration in the material following each
irradiation signal during the same logging run, at least one gate
means for transmitting signals from the detector means during at
least one measurement interval, comparing means responsive to the
neutron concentration indication signals transmitted by the gate
means to produce a comparison signal related to the neutron
concentration in the material at the measurement time, and control
means responsive to the comparison signal to produce a control
signal for controlling automatically the operation of the neutron
source means.
29. Apparatus according to claim 28 wherein the control means
.[.include.]. includes means for producing a control signal which
controls the duration of the irradiation interval.
30. Apparatus according to claim 28 wherein the control means
includes means for producing a control signal which controls the
spacing of successive irradiation intervals.
31. Apparatus for logging a characteristic of an unknown material
comprising neutron source means for irradiating the material with
neutrons for an irradiation interval upon receipt of a control
signal, detector means for producing indications of the neutron
concentration in the material following each irradiation signal
during the same logging run, at least one variable gate means for
transmitting signals from the detector means during at least one
measurement interval at a measurement time, at least one of the
measurement interval and the measurement time being variable,
comparing means responsive to the neutron concentration indication
signals transmitted by the gate means to produce a comparison
signal related to the neutron concentration in the material at the
measurement time, and control means responsive to the comparison
signal to produce a control signal for controlling automatically
the operation of the variable gate means.
32. Apparatus according to claim 31 wherein the control means
includes means for producing a control signal which controls the
duration of the measurement interval.
33. Apparatus according to claim 31 wherein the control means
includes means for producing a control signal which controls the
selected measurement time. .Iadd. 34. A method for logging a
characteristic of material adjacent a well bore, comprising:
irradiating the material with neutrons during an irradiation
interval;
measuring detected indications of the concentration of neutrons in
the material during each of first and second measuring intervals
occurring at first and second times, respectively, after
commencement of the irradiation interval;
measuring detected indications of background radiation in the
material during a third measuring interval occurring in the same
logging run at a third time after commencement of the irradiation
interval; and
combining the measurements made during the first, second and third
measuring intervals to determine a background corrected neutron
characteristic of the material. 35. A method according to claim 34
wherein the time of occurrence of the third measuring interval is
after the termination of the first and second measuring intervals.
36. A method according to claim 35 wherein:
the times of occurrence of the first and second measuring intervals
are set to provide measurements of gamma rays resulting from
capture of thermal neutrons and indicative of the concentration of
thermal neutrons in the
material during the first and second measuring intervals. 37. A
method according to claim 36 wherein the neutron characteristic
determined is the thermal neutron decay time of the material, and
the time of occurrence of at least said third measuring interval is
varied as a function of the thermal neutron decay time. 38. A
method according to claim 34 wherein the combining of the first,
second and third interval measurements includes subtracting a
function of the third interval measurement from the first and
second interval measurements to provide background-corrected first
and second interval measurements. 39. A method according to claim
38 wherein the combining of the first, second and third interval
measurements further includes deriving a ratio function of the
background-corrected first and second interval measurements to
determine the background-corrected neutron characteristic. 40. A
method according to claim 38 wherein the third interval measurement
is subtracted from each of the first and second interval
measurements in proportion to the respective durations of the first
and second measuring intervals. 41. A method according to claim 34
wherein the step of combining the first, second and third interval
measurements comprises:
determining an indication of the rate of decay of at least a
portion of the neutron population in the material from the first
and second interval measurements; and
correcting the indication of the neutron decay rate in accordance
with the third interval measurement to provide a
background-corrected indication of
the decay rate. 42. A method according to claim 41 wherein the
neutron decay rate indication is corrected by subtracting a
function of the third interval measurement from the neutron
concentration measurements of the first and second measuring
intervals. 43. A method for logging a characteristic of material
adjacent a well bore, comprising:
irradiating the material with neutrons during a timed sequence of
time-spaced irradiation intervals;
measuring detected indications of the concentration of neutrons in
the material during each of first and second measuring intervals
occurring at first and second times, respectively, after
corresponding irradiation intervals;
measuring detected indications of background radiation in the
material during a third measuring interval at a third time
occurring after first and second measuring intervals following each
irradiation interval and prior to the next successive irradiation
interval; and
combining the measurements made during the first, second and third
measuring intervals to determine a background corrected neutron
chracteristic of the material. 44. A method according to claim 43
wherein the third measuring interval occurs immediately before the
next successive irradiation interval. 45. A method according to
claim 43 wherein the neutron characteristic determined is the
thermal neutron decay time of the material, the timing of at least
one of said irradiation internal and first, second and third
measuring intervals in successive sequences being varied as a
function of decay time determined in prior sequences. 46. A method
for logging a characteristic of material adjacent a well bore,
comprising:
irradiating the material with discrete bursts of neutrons in a
timed sequence;
measuring detected indications of the concentration of neutrons in
the material during each of first and second measuring intervals
occurring at first and second times, respectively, during the time
period between the commencement of each neutron burst and the
commencement of the next successive neutron burst;
suppressing a subsequent neutron burst in the timed sequence;
measuring detected indications of background radiation in the
material during a third measuring interval occurring during the
time period between the predetermined time of commencement of the
suppressed neutron burst and the commencement of the next
unsuppressed neutron burst; and
combining the measurements made during the first, second and third
measuring intervals to determine a background-corrected neutron
characteristic of the material. 47. A method according to claim 46
wherein the combining of the first, second and third interval
measurements includes subtracting a function of the third interval
measurement from the first and second interval measurements to
provide background-corrected first and second interval
measurements. 48. A method according to claim 47 wherein the third
interval measurement is subtracted from each of the first and
second interval measurements in proportion to the respective
durations of the first and second measuring intervals. 49. A method
according to claim 46 wherein the second measuring interval
immediately precedes the time of commencement of suppressed or
unsuppressed neutron bursts in the sequence. 50. Apparatus for
logging a characteristic of material adjacent a well bore,
comprising:
control means for timing a sequence of intervals during which the
material is irradiated with neutrons;
means for measuring detected indications of the concentration of
neutrons in the material during each of rist and second measuring
intervals occurring at first and second times, respectively, after
commencement of respective irradiation intervals;
means for measuring detected indications of background radiation in
the material during a third measuring interval occurring at a third
time between successive irradiation intervals; and
means for combining the measurements made during the first, second
and third intervals to determine a background-corrected neutron
chracteristic
of the material. 51. Apparatus according to claim 50 wherein the
means for measuring detected indications of neutron concentration
includes first and second gate means for transmitting detected
indications of the neutron concentration during said first and
second measuring intervals, respectively, and
means for measuring detected indications of background radiation
includes third gate means for transmitting detected indications of
background radiation during said third measuring interval, the
third gate means being operative to place the time of occurrence of
the third measuring interval in sequence following the first and
second measuring intervals between successive irradiation
intervals. 52. Apparatus according to claim 50 wherein the
combining means includes means for subtracting a function of the
third interval measurement from the first and second interval
measurements to provide background-corrected first and second
interval
measurements. 53. Apparatus according to claim 52 wherein the
subtracting means is operative to subtract the third interval
measurement from the first and second interval measurements in
proportion to the respective durations of the first and second
measuring intervals; and
wherein the combining means further includes means for deriving a
ratio function of the background-corrected first and second
interval measurements to determine a background-corrected neutron
characteristic. 54. Apparatus according to claim 50 wherein the
combining means includes:
means responsive to the first and second interval measurements for
determining an indication of the rate of decay of at least a
portion of the neutron population in the material; and
means for correcting the indication of the neutron decay rate in
accordance with the third interval measurement to provide a
background-corrected indication of the decay rate. 55. Apparatus
according to claim 54 wherein the correcting means is operative to
subtract a function of the third interval measurement from the
neutron concentration measurements of the
first and second measuring intervals. 56. Apparatus according to
claim 50 wherein the combining means determines the thermal neutron
decay time of the material; and
wherein the timing means varies the occurrence of at least one of
the measuring intervals in successive sequences as a function of
the thermal neutron decay time determined in prior sequences. 57.
Apparatus according to claim 56 wherein said timing means varies
the occurrence of each of the measuring intervals in successive
sequences as a function of the thermal neutron decay time
determined in prior sequences. 58. Apparatus according to claim 56
wherein said timing means also varies the occurrence of the
irradiation intervals in successive sequences as a function of the
thermal neutron decay time determined in prior sequences. 59.
Apparatus according to claim 50 wherein the timing means controls
the timed sequence of at least said measuring intervals to place
the third measuring interval after the second measuring interval
and immediately before the next irradiation interval. 60. Apparatus
for logging a characteristic of a material adjacent a well bore,
comprising:
means for irradiating the material with discrete bursts of neutrons
in a predetermined sequence;
means for measuring detected indications of the concentration of
neutrons in the material during each of first and second measuring
intervals occurring at first and second times, respectively, during
the time period between the commencement of each neutron burst and
the commencement of the next successive neutron burst;
means for suppressing a subsequent neutron burst in the timed
sequence;
means for measuring detected indications of background radiation in
the material during a third measuring interval occurring during the
time period between the predetermined time of commencement of the
suppressed neutron burst and the commencement of the next
unsuppressed neutron burst; and
means for combining the measurements made during the first, second
and third measuring intervals to determine a background-corrected
neutron characteristic of the material. 61. Apparatus according to
claim 60 wherein the third interval measuring means includes means
for commencing and terminating the third measuring interval in
substantial coincidence with the time of commencement of the
suppressed neutron burst and the commencement of the next
unsuppressed neutron burst. 62. Apparatus according to claim 60
wherein the third interval measuring means includes means for
commencing the third measuring interval at the predetermined time
of termination of the suppressed neutron burst and terminating it
at
the time of commencement of the next unsuppressed neutron burst.
63. Apparatus according to claim 22 including variable gate means
responsive to the synchronizing signals and the neutron
concentration indication signals for transmitting background
indication signals during a measurement interval occurring at a
time after receipt of a synchronizing signal later than the one
measurement time;
said comparing means being responsive to the background indication
signals to provide background correction for said comparison
signal. 64. Apparatus according to claim 31 including variable gate
means for transmitting background indication signals from the
detector means during a background measurement interval at a time
later than said measurement time;
said comparing means being responsive to the background indication
signals to provide background correction for said comparison
signal. 65. Apparatus according to claim 64 wherein the comparing
means includes means for subtracting a function of the background
indication signals from the neutron concentration indication
signals to provide background correction. 66. Apparatus according
to claim 65 wherein the subtracting means is operative to subtract
the background indication signals from the neutron concentration
indication signals in proportion to the duration of the
neutron concentration measurement interval. 67. A method according
to claim 18 wherein the measurement obtained during the third
measurement interval is subtracted from the measurements obtained
during the first and second measurement intervals in proportion to
the respective durations of the first and second measurement
intervals. .Iaddend.
Description
This invention relates to measurement of the neutron characteristic
time constants of an unknown material such as the decay time of
thermal neutrons therein and, more particularly, to a new and
improved method and apparatus for measuring neutron characteristic
time constants more accurately and rapidly.
One procedure for determining the character of unknown materials,
such as the earth formations through which a well bore passes,
comprises irradiating the material with neutrons for a selected
period of time and then determining the concentration of neutrons
in the material at selected times after irradiation so that a
neutron characteristic time constant of the material maybe
ascertained. Because the various elements capture thermal neutrons
at different rates, the change of thermal neutron concentrations
with time following irradiation will be different for materials
containing different elements so that a determination of the rate
of capture can be used to give an indication of the type of
material irradiated. Usually, this neutron characteristic of the
material is expressed as the thermal neutron decay time, which is
the time required for the thermal neutron concentration to decrease
by a factor equal to the natural logarithm base e which is 2.718.
In another procedure the characteristic of the material known as
the neutron slowing down time is determined by measuring the
concentration of higher energy neutrons at various times after
irradiation.
When the earth formation material adjacent to a well bore is being
analyzed, the variation of neutron concentration with time during
the period immediately following irradiation is influenced to a
large extent by material in the well bore. As the thermal neutron
intensity reaches a low level, moreover, measurements are altered
by background and noise effects. Consequently, there is only a
certain period of time during which the neutron characteristic time
constants such as the thermal neutron decay time of the formation
material can be determined accurately. The rate of decay of thermal
neutrons with time and the slowing down time of higher energy
neutrons vary widely for different formation materials, however, so
that the proper time interval following neutron irradiation for
characteristic time constant measurements is not the same for
different formations and, heretofore, it has been necessary to
measure the neutron concentration at many different times after
neutron irradiation in order to obtain an accurate determination of
a neutron characteristic time constant.
Accordingly, it is an object of the present invention to provide a
new and improved method for measuring neutron characteristic time
constants which overcomes the above-mentioned disadvantages of
present methods.
Another object of the invention is to provide a new and improved
apparatus giving immediate and accurate indications of the thermal
neutron decay time of a material being analyzed.
These and other objects of the invention are attained by measuring
the rate of change of the neutron intensity so as to indicate the
neutron characteristic time constant of the material at a time
after neutron irradiation which is dependent upon the
characteristic time constant of the material. In this way, thermal
neutron decay time measurements, for example, can be made at the
proper time for all materials regardless of whether the thermal
neutron concentration decreases rapidly or slowly. Moreover, the
durations of the time intervals during which the neutron
characteristic time constant measurements are made are also varied
in accordance with the time constant of the materials so that the
ratio of the neutron counting rates is a predetermined number when
the time intervals are properly selected. For optimum operation,
the duration of the neutron irradiation intervals are also
proportional to the time constant.
In a particular embodiment for thermal neutron decay time
measurements utilizing continuously repetitive bursts of neutron
irradiation spaced at intervals about nine decay times in length, a
first thermal neutron count is taken during an interval one decay
time long which begins two decay times after the irradiation has
stopped and a second thermal neutron count is taken during a second
interval immediately after the first interval which is two decay
times long. Preferably, the thermal neutron intensity may be
measured by a detector which detects the capture gamma rays
produced in the formation. With this type of detector, it is
preferable to take a background count during an interval beginning
at least seven decay times after the neutron irradiation has
stopped. This background count is subtracted from both of the first
and second interval counts in proportion to their duration. In
another embodiment, improved results are obtained by spacing the
first and second time intervals by one decay period. In this case,
every fourth neutron burst is omitted and the background is
measured only during a period at least eight decay times after the
third burst, the three neutron bursts being two decay times .[.
along.]. .Iadd.long .Iaddend.and occurring at intervals of eight
decay times.
In the first embodiment, when the adjacent time intervals are
properly set at one and two decay times, respectively, the ratio of
the counting rate in the first interval to the counting rate in the
second interval is a fixed number 1.99. Consequently, the time
intervals are adjusted in a two to one ratio until the ratio of
counting rates equals 1.99 and the delay between irradiation and
measurement is adjusted to be twice the first time interval. In the
second embodiment the procedure is similar except the intervals are
adjusted to obtain a counting rate ratio of 5.40.
Apparatus for determining thermal neutron decay times according to
the invention includes a variable oscillator for initiating and
terminating the measurement intervals. The period of this
oscillator determines the ratio of thermal neutron counting rates
in the first and second intervals. Preferably, the oscillator
controls two gates arranged to transmit pulses from a radiation
detector during the first and second intervals and also operates a
third gate at a later time to provide background count information.
The background counting rate is subtracted from the counting rates
during the first and second time intervals and a ratio detector
computes the ratio of the net counting rates. A difference circuit
responds to any difference between the measured counting rate ratio
and the value which must result when the first and second intervals
are one and two decay times, respectively, and adjusts the
oscillator in the proper direction to eliminate any difference.
Further objects and advantages of the invention will be apparent
from a reading of the following description in conjunction with the
accompanying drawings in which:
FIG. 1 is a graphical representation illustrating the variation in
counting rate versus time after neutron irradiation for three
different types of earth formation surrounding a well bore as
detected by a radiation detector disposed in the well bore and
adapted to respond to indications of thermal neutron intensity;
FIG. 2 is a graphical representation showing the variation in
indicated decay time versus time after neutron irradiation for the
three curves shown in FIG. 1;
FIG. 3 is a graphical representation showing a family of curves
having different scale factors;
FIG. 4 is a graphical representation showing the variation in the
ratio of selected areas under the curves of FIG. 3 with changes in
the scale of measurement.
FIG. 5 is a graphical representation of detector counting rate
versus time illustrating one embodiment of the method for
determining thermal neutron decay time according to the
invention;
FIG. 6 is a graphical representation of detector counting rate
versus time illustrating another embodiment of the method for
determining thermal neutron decay time; and
FIG. 7 is a schematic block diagram illustrating a representative
apparatus for measuring thermal neutron decay times according to
the invention.
In the graphical representation of FIG. 1, three curves 10, 11 and
12 represent, respectively, the logarithm of the counting rate
after background subtraction versus time for a detector of thermal
neutrons or of neutron capture gamma rays disposed in a well bore
following neutron irradiation of formations having short, medium
and long decay times or rates of decrease of thermal neutron
intensity. The curve 10 represents the response of a 40 percent
porous sandstone formation containing brackish water having about
250,000 p.p.m. of salt, while the curve 11 indicates the response
of 18 percent porous sandstone containing oil and water, the curve
12 showing the response obtained from zero porosity sandstone. For
purposes of comparison, the curves of FIG. 1 have been normalized
to approximately the same peak counting rate although, in actual
practice, this does not generally occur. The variation in counting
rate with respect to time may, in each case, be expressed as a
function M(t) and at any time t, the decay time .tau. is defined as
##EQU1## When M(t) is a decreasing exponential function, .tau. is a
constant equal to the time required for the counting rate to
decrease by the factor e.
It will be readily apparent that the decay time .tau. will vary
with time whenever the logarithm of counting rate versus time as
represented in FIG. 1 is not a straight line. In this regard, the
curves 14, 15 and 16 of FIG. 2 illustrate the variation in .tau.
with time for the typical counting rate curves 10, 11 and 12 of
FIG. 1. It will be observed from these curves that, in each case,
the decay time curve has an initial portion 14a, 15a, 16a which
increases with time a central portion 14b, 15b, 16b in which the
decay time is substantially constant and a final portion 14c, 15c,
16c in which the decay time again increases with time. Because the
constant decay time portions 14b, 15b, .Iadd.and .Iaddend.16b,
which most closely represent the actual decay time of the formation
material, do not occur at the same time, it is impossible to select
any specific time interval after neutron irradiation for
measurement of decay times which will provide an accurate decay
time indication for all types of earth formations. For example, the
proper time interval for measuring the decay time of the material
producing the curve 14 is about 200 to 500 microseconds after
irradiation, whereas that for the curve 15 is about 1,000 to 2,500
microseconds after irradiation and that for the curve 16 is about
1,800 to 4,500 microseconds after irradiation.
In accordance with the invention, therefore, the decay time
measurement is made at a time after irradiation which is dependent
upon the value of the decay time so that the time of measurement
coincides with the time at which the curve provides an accurate
decay time indication, i.e., where the decay time is substantially
constant. Stated another way, the amplitude and time scales of the
curves 10, 11 and 12 are each changed by factors which cause the
curves to coincide over the regions which correspond to the central
region 14b, 15b, and 16b, of the corresponding curves in FIG. 2 the
time scale factor for each curve being the decay time .tau. for the
curve. Inasmuch as the time scale factor must be .tau. to provide
the desired result, let the counting rate corresponding to a
particular curve be ##EQU2## where ##EQU3## In this notation the
term (i) is used as superscript and not as an exponent. Since the
various functions Mi(t) differ by scale factors in both time and
amplitude in the constant .tau. region, the appropriate time scale
factors .tau..sub.i and amplitude scale factors A, define for each
function Mi(t) a corresponding function A.sub.i
.[.Ni.]..Iadd.N.sub.i.Iaddend. (x.sup.(i)). A family of such curves
is shown in FIG. 3. In the constant .tau. region of interest,
however, these functions are approximated by the function N(x) =
Ae.sup.-.sup.x, (4) as indicated by the common portion 13 of the
curves in FIG. 3.
In order to determine the scale factor .tau. for any given counting
rate curve, the ratio of the areas under the asymptotic curve
Ae.sup.-.sup.x for two adjoining x intervals I.sub.x andn II.sub.x
in the common region 13 is determined. The relative position and
widths of the intervals are chosen to optimize the accuracy of the
decay time measurement. For the first embodiment the positions of
the interval boundaries are depicted on FIG. 3 wherein they are
defined to be in a specific proportion to a single parameter
X.sub.1. The ratio of the areas R is therefore a monotonically
increasing function of X.sub.1 which is shown on FIG. 4 by the
curve 13a. Therefore any desired position of the X intervals and in
particular the region 13 on FIG. 3, can be selected by specifying
the associated value of R.
As indicated by equation (3), for constant .tau. as occurs in the
central region of each of the thermal neutron decay curves 10, 11
and 12, there will be two corresponding time intervals I.sub.t and
II.sub.t for which the ratio of the areas under the curves, i.e.,
the ratio of counting rates during the time intervals, will be the
same as the ratio of the areas I.sub.x and II.sub.x under the curve
Ae.sup.-.sup.x. The correct value of the scale factor for each
curve which will cause this equality of the counting rate ratio
curve to the asymptotic ratio curve is the decay time .tau.. The
measurement is performed by maintaining the counting intervals and
the interval from the end of irradiation to the first counting
interval in the same fixed proportion to a time parameter t.sub.1
as the corresponding x intervals bear to the parameter X.sub.1. The
parameter t.sub.1 is then varied until the ratio of the interval
counting rates is equal to the selected value Ro.
The required scale factor or decay time .tau..sub.i is then
obtained from equation (3) by substituting X.sup.(i) the value of
X.sub.1 associated with Ro and for the value of t.sub.1 which
produces the counting rate ratio equal to Ro and solving for .Iadd.
t .Iaddend..tau..sub.i. Since the functions AiNi (X.sup.(i))
essentially coincide with Ae.sup.-.sup.x in the region 13 on FIG.
3, the value of .tau..sub.i determined in this manner will be
unique and will not vary substantially with the particular value
selected for Ro provided that it corresponds to intervals in the
asymptotic region 13 on FIG. 3.
Consideration of the shape of the counting rate function indicates
that the most accurate determinations of the scale factor are
provided when the counting intervals begin at least two decay times
after termination of the neutron irradiation and the second
counting interval is longer than the first. In a particular example
illustrated in FIG. 5 wherein neutron irradiation bursts 17 and 18
are provided at nine decay time intervals as a downhole instrument
is moved through the well bore, the curve 19 represents the thermal
neutron count as measured by a detector in the well bore at
subsequent times indicated in terms of the decay time .tau.. As a
practical matter, the decay time usually varies between about 70
microseconds and about 1,000 microseconds depending upon the nature
of the formation material as indicated by FIG. 2, so that the
separation of nine decay periods from the beginning of one neutron
burst to the beginning of the next may be as low as about 630
microseconds for formations having a rapidly decaying thermal
neutron concentration and as high as about 9,000 microseconds for
formations having slowly decaying thermal neutron concentration.
Moreover, the length of the neutron irradiation periods 17 and 18
is also scaled according to the decay time of the formation and, in
the illustrated example, the neutron irradiation lasts for an
interval of two decay times. Where more intense neutron irradiation
is possible, however, the duration of neutron irradiation may be
reduced so as to leave more time for measurement between
irradiation bursts, or closer spacing of bursts.
In the example of FIG. 5, optimum measurement of the decay time is
obtained by initiating the first counting rate measurement interval
20 two decay times after termination of the irradiation burst 17
and making that interval one decay time long. The second counting
rate measurement interval 21 commences immediately after the first
and is two decay times long while the remaining interval 22 of two
decay times before the next irradiation period 18 is used to
provide a measurement of the background counting rate. After
subtraction of the counting rate in the interval 22 from that in
the interval 21 and one-half of the interval 22 counting rate from
that in the interval 20, the ratio of the net counting rates in the
first two intervals is taken.
For an exponential decrease in counting rate as occurs in the
central section of the curve 19, the ratio of the net counting
rates in the intervals 20 and 21 should be 1.99 if the time
intervals are actually one decay time and two decay times long,
respectively. Accordingly, the time scale of the measuring
operation is adjusted until the ratio of counting rates is equal to
about 1.99 and, when that condition obtains, the duration of the
first measuring time interval 20 is equal to the decay time. This
may be indicated either by providing a signal representing the
number of microseconds elapsed during the first counting interval
or, where the time scale is varied by utilization of a variable
frequency oscillator, as in the example described hereinafter, by
providing an output signal having an inverse relation to the
frequency of the oscillator. The macroscopic capture cross section
is inversely proportional to the decay time and may therefore be
obtained by bringing out a signal proportional to the oscillator
frequency.
The accuracy of determination of the decay time may be increased,
if desired, by separating the first and second measurement
intervals somewhat. In the further embodiment of the invention
shown in FIG. 6, the first counting rate measuring interval 23 is
one decay time long and starts two decay times after the end of the
neutron burst 24 which is two decay times long as in the previous
embodiment. In this case, an interval of time 25, which is one
decay time long, separates the first counting interval 23 from the
second counting interval 26, the latter being two decay times in
length. This procedure has been found to reduce the uncertainty in
measured decay time to about 60 percent of that obtained when the
example illustrated in FIG. 3 is used when the background counting
rate is relatively low.
In order to provide a background counting rate measurement which is
affected less by the decaying counting rate caused by the thermal
decay process, the neutron irradiation bursts in the FIG. 6 example
occur at intervals of eight decay times, except that every fourth
irradiation burst 27 is suppressed and the background counting rate
is measured in an interval 28 six decay times long which starts at
the end of the suppressed neutron burst 27. This background
counting rate is subtracted from the measurements made during the
second interval 26 following each of the three succeeding
irradiation bursts, after which another background counting rate
measurement is made when the next irradiation burst is omitted.
Similarly, this background counting rate is divided by two for
proper normalization before it is subtracted from the counting rate
measured during first rate interval 23 following each of the three
succeeding irradiation bursts. For an asymptotic curve, the ratio
of the areas in first and second intervals corresponding to the
intervals 23 and 26 is approximately 5.40. Accordingly, in this
case, the time scale of the measurement is adjusted until the ratio
of net counting rates in the intervals 23 and 26 is 5.40 and, when
that condition obtains, the duration of the first interval 23 is
equal to the decay time.
In a representative arrangement of apparatus for measuring decay
times according to the invention illustrated in FIG. 7, a downhole
instrument 30 is drawn through a well bore 31 by a multiconductor
cable 32. Within the instrument 30, a burst neutron source 33,
which may be of the type described in the U.S. Pat. No. 2,991,364
issued .[.Jul..]. .Iadd.July .Iaddend. 4, 1961, to Goodman, for
"Well Logging," is positioned to irradiate the formation 34
adjacent to the well bore with neutrons. In addition, a radiation
detector 35 is disposed within the instrument 31 in spaced relation
above the source 33 and is positioned to respond in proportion to
the concentration of thermal neutrons in the formation 34. In this
regard, the detector 35 may be either a detector of thermal
neutrons as, for example, a scintillation crystal coated with boron
trifluoride or it may be a gamma ray detector adapted to respond to
gamma rays resulting from capture of thermal neutrons by nuclei of
elements in the formation 34.
At the surface of the earth, a variable frequency oscillator 36
produces output pulses on a line 37 which are separated by equal
time intervals T.sub.o, the time intervals being controlled in
duration by a signal on a control line 38 from an oscillator
control unit 39. A counter 40, receiving time signals from a clock
41, is actuated by the oscillator output signals on the line 37 at
intervals T.sub.o to transmit to a T.sub.o indicator 42 a signal
indicating the number of microseconds in the intervals T.sub.o.
When the ratio of counting rates in the two counting intervals is
correct, this number is equal to the decay time .tau. of the
formation as explained above.
Five factor units 43, 44, 45, 46 and 47 which may, for example,
contain conventional flip-flop circuits connected in series to the
line 37, successively increase the period of the oscillator output
signal by factors of two so that the output signals from these
units occur at intervals of 2T.sub.o, 4T.sub.o, 8T.sub.o,
16T.sub.o, and 32T.sub.o respectively. In order to control the time
intervals in which neutron irradiation and subsequent thermal
neutron concentration measurement takes place, a network of logic
gates 48 receives signals from the oscillator 37 and from the units
43, 44, 45, 46 and 47 and is arranged to provide output signals at
the required times. The logic gate network may be arranged in any
conventional manner to accomplish the desired result as by
utilizing appropriate gates and additional flip-flop units.
The typical apparatus illustrated in FIG. 7 is arranged to operate
in the manner described in connection with FIG. 6 irradiating at
intervals of eight decay times with every fourth neutron burst
suppressed, the background counting rate being measured after the
third neutron irradiation. Accordingly, the logic gate network 48
has four output conductors 49, 50, 51 and 52 providing signals at
selected intervals according to the sequence indicated in FIG. 6,
the logic network being reset at 32T.sub.o to initiate another
series of irradiation and measurement cycles. Operation of the
pulsed neutron source 33 is controlled by signals on the line 52
from the unit 48 so as to initiate irradiation for a time 2T.sub.o
at intervals of 8T.sub.o except when irradiation is omitted at the
time 24T.sub.o.
Signals from the radiation detector 35 representing the thermal
neutron concentration in the formation 34 following neutron
irradiation are transmitted by way of a conductor 56 to three gate
units 57, 58 and 59. The gate 57, opened at times 4T.sub.o,
12T.sub.o, and 20T.sub.o, and closed at 5T.sub.o, 13T.sub.o and
21T.sub.o respectively transmits signals on the line 49 signals
representing the counting rate during the first measuring interval
designated 23 in FIG. 6 in each of the first three 8T.sub.o cycles
of operation. Similarly, the gate 58, opened at 6T.sub.o, 14T.sub.o
and 22T.sub.o, and closed at 8T.sub.o, 16T.sub.o and 24T.sub.o by
signals on the line 50, transmits signals representing the counting
rate during the second interval designated 26 in FIG. 6 in each of
the first three 8T.sub.o cycles of operation.
After the time when the fourth neutron irradiation burst has been
suppressed at 24T.sub.o, the gate 59 is opened at 26T.sub.o and
closed at 32T.sub.o by signals on the line 51 so as to transmit the
background counting rate during the interval designated 28 in FIG.
6. It will be understood, of course, that the background counting
rate may be measured at any time after 24T.sub.o and, if necessary
to provide a high enough counting rate, it may be measured during
the entire period from 24T.sub.o to 32T.sub.o. This signal is
transmitted through a flip-flop 60, which divides the count rate by
two, to a rate counter 61 and directly to a reference counter 62,
the counters 61 and 62 also being connected to receive signals from
the gates 57 and 58 respectively. These counters may be
conventional bidirectional or "forward and backward" counters,
which count in the forward direction when they receive signals from
the gates 57 and 58, respectively, and count in the backward
direction when they receive signals from the background gate
59.
The ratio of the differences representing the net thermal neutron
concentration in the intervals 23 and 26 is determined by reading
out the count in the rate counter when the reference counter has
reached a predetermined value as detected by a read gate 63. Both
the counters are reset to specific initial states after each
readout but the net count accumulated in the rate counter at the
time of readout is transferred to a buffer storage unit 64. Since
the net count in the reference counter is equal to the same
predetermined value at each readout, the numbers stored in the
buffer storage unit 64 at each readout are proportional to the
value of the ratio R of net counting rates in the intervals 23 and
26. The count in the buffer storage 64 is converted to an analogue
voltage in a digital to analogue converter unit 65, the output of
which is therefore proportional to the aforesaid counting rate
ratio R. A comparing unit 66 compares this measured counting rate
ratio with a fixed reference ratio R.sub.o which, in the
illustrated example, is 5.40 and any difference is amplified by an
amplifier 67 and supplied to the oscillator control unit 39. That
unit, in turn, changes the frequency of the variable oscillator 36
by way of the control line 38 to maintain the difference between R
and R.sub.o as close to zero as possible. In this condition, the
reading of the oscillator period T.sub.o on the indicator 42 is
substantially equal to the decay time characterizing the formation
being irradiated as exemplified in the curves 10, 11 and 12 of FIG.
1. If desired, the decay time may also be indicated by taking the
reciprocal of the oscillator frequency as commanded by the
oscillator control line 38. Moreover, either the indicator 42 or an
indicator of the reciprocal of oscillator frequency, or both, may
be arranged to record the decay time continuously against depth as
the instrument 30 moves through the well bore. The information
processing features of the embodiment of the invention shown in
FIG. 6 can be accomplished by an arrangement of known digital,
analogue or hybrid computer components.
In operation, as the downhole instrument 30 is drawn upwardly in
the well bore 31 by the cable 32, the neutron source 33 is pulsed
at intervals under the control of signals on the line 52. The
resulting indications of thermal neutron concentration produced by
the detector 35 are transmitted over the conductor 56 to the gates
57, 58 and 59. Subtraction of the background counting rate detected
by the gate 59 in proportion to the length of the intervals 23 and
26 provides a net counting rate for each interval and the ratio
taken by the unit 65 after a selected count is attained in the
second interval is compared in the unit 66 to a desired ratio
value. Any difference between these values causes the oscillator
control unit 39 to correct the frequency of the variable oscillator
36 so that its period is equal to the thermal neutron decay time of
the formation.
From the foregoing, it will be apparent that the method and
apparatus of the present invention provide not only an extremely
simple way of measuring thermal neutron decay times which yields an
immediate result but also one in which the determination is more
accurate because the durations of neutron irradiation bursts and of
counting rate detection intervals and times are varied in
accordance with the decay time, thereby permitting detection at the
optimum time in each decay curve and allowing higher counting rates
in every instance. It will be understood, moreover, that the method
and apparatus of the invention may be used for measuring other
neutron characteristic time constants of a material than thermal
neutron decay time as, for example, the neutron slowing down
time.
Although the invention has been described herein with reference to
specific embodiments, many modifications and variations therein
will readily occur to those skilled in the art. Accordingly, all
such variations and modifications are included within the intended
scope of the invention as defined by the following claims.
* * * * *