CA2497355A1 - Spectral gamma ray logging-while-drilling system - Google Patents

Spectral gamma ray logging-while-drilling system Download PDF

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Publication number
CA2497355A1
CA2497355A1 CA002497355A CA2497355A CA2497355A1 CA 2497355 A1 CA2497355 A1 CA 2497355A1 CA 002497355 A CA002497355 A CA 002497355A CA 2497355 A CA2497355 A CA 2497355A CA 2497355 A1 CA2497355 A1 CA 2497355A1
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Prior art keywords
detector
gain
spectrum
gamma ray
borehole
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CA002497355A
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French (fr)
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CA2497355C (en
Inventor
Medhat Mickael
Dale Jones
Donald Phelps
John Wright
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Weatherford Canada Ltd
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Precision Drilling Technology Services Group Inc
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Priority to CA2842939A priority Critical patent/CA2842939A1/en
Priority to CA2842938A priority patent/CA2842938C/en
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    • GPHYSICS
    • G01MEASURING; TESTING
    • G01VGEOPHYSICS; GRAVITATIONAL MEASUREMENTS; DETECTING MASSES OR OBJECTS; TAGS
    • G01V5/00Prospecting or detecting by the use of nuclear radiation, e.g. of natural or induced radioactivity
    • G01V5/04Prospecting or detecting by the use of nuclear radiation, e.g. of natural or induced radioactivity specially adapted for well-logging
    • G01V5/06Prospecting or detecting by the use of nuclear radiation, e.g. of natural or induced radioactivity specially adapted for well-logging for detecting naturally radioactive minerals
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01VGEOPHYSICS; GRAVITATIONAL MEASUREMENTS; DETECTING MASSES OR OBJECTS; TAGS
    • G01V5/00Prospecting or detecting by the use of nuclear radiation, e.g. of natural or induced radioactivity
    • G01V5/04Prospecting or detecting by the use of nuclear radiation, e.g. of natural or induced radioactivity specially adapted for well-logging
    • G01V5/08Prospecting or detecting by the use of nuclear radiation, e.g. of natural or induced radioactivity specially adapted for well-logging using primary nuclear radiation sources or X-rays
    • G01V5/12Prospecting or detecting by the use of nuclear radiation, e.g. of natural or induced radioactivity specially adapted for well-logging using primary nuclear radiation sources or X-rays using gamma or X-ray sources
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01VGEOPHYSICS; GRAVITATIONAL MEASUREMENTS; DETECTING MASSES OR OBJECTS; TAGS
    • G01V5/00Prospecting or detecting by the use of nuclear radiation, e.g. of natural or induced radioactivity
    • G01V5/04Prospecting or detecting by the use of nuclear radiation, e.g. of natural or induced radioactivity specially adapted for well-logging
    • G01V5/08Prospecting or detecting by the use of nuclear radiation, e.g. of natural or induced radioactivity specially adapted for well-logging using primary nuclear radiation sources or X-rays
    • G01V5/12Prospecting or detecting by the use of nuclear radiation, e.g. of natural or induced radioactivity specially adapted for well-logging using primary nuclear radiation sources or X-rays using gamma or X-ray sources
    • G01V5/125Prospecting or detecting by the use of nuclear radiation, e.g. of natural or induced radioactivity specially adapted for well-logging using primary nuclear radiation sources or X-rays using gamma or X-ray sources and detecting the secondary gamma- or X-rays in different places along the bore hole

Abstract

A method for determining concentrations of naturally occurring radioactive elements in earth formation by analysis of gamma ray energy spectra measured by at least one gamma ray detector while the borehole is being drilled. Gain of the gamma ray detector is controlled automatically through analysis of the spectra. The one or more gamma ray detectors are disposed at the periphery of the downhole instrumentation to maximize sensitivity. Elemental concentrations of naturally occurring radioactive elements such as potassium, uranium and thorium are measured either as a function of depth in the borehole, or as a function of aximuthal sectors around the borehole wall, or as a function of both depth and azimuthal sectors.

Description

SPECTRAL GAMMA RAY LOGGINGWBILE-DxB.f.ING SYSTEM
This invention is direct~d toward the measure of gamma radiation from earth formation pen~t~ by a well boreholO. More particularly, the invention is directed toward the determination of concentrations of natinally occturing radioactive elements in earth formation by analysis of energy spectra measured by at least ono gamma ray detector while the boirhole is being .
BACKGROUND OF TIC nW8N7~ION
The measure of nattnsily oc~ing gamma radiation as a function of depth within a well borehole is the basis of one of the earliest borehole geophysical exploration system. This type system, commonly refe~ed to as a nabn~l ,~na ray logging system, typically comprises at least one gamma ray doctor housed in a dowahole tool that is conveyed along the boTahole.
One type of natural gamma ray logging system con~prisea a logging tool that is responsive to total gamma radiation emitted by the earth formation, aad the tool is conveyed along the bomeholo by means of a vvimhimo. This "total" nadnal gamma ray wireline logging system was the first type of gamma ray measurement usad in borohole geophysical exploration. Sinx most abates are relatively rich in nat<nally aoaaring radioactive elements, these logs are used primarily to delineate shale from other formations, or used to measure the shale content of formations. This vviroline logging system is used only after the baroholo has boon drillofl Ii is often advantageous to measure total natiwal gamma radiation while the barehole is being drilled. This is acc~nplished by conveying the tool along the borebole by means of a drill string. This type of s3~stom is commonly referned to as a total natural gamma ray logging-whilo-drilling (LSD) systenn.
Yet another typo of natural gamma ray logging system comprises a logging tool that measures a spectrum of gamma radiation emitted by the earth formation.
The ap~rum is defined a measure of intensity of radiation as a function of radiation energy.
This type of logging system is commonly referred to as a spech~al gamma ray logging system Spectral gamma ray logging tools ane typically conveyed along the borehole by means of a wireline. Low count rate and detector stabilization are major problems in any type of natural spectral LWD systems Most naturally occurring gamma radiation found in earth formations is emitted by potassium (I~ and elements within the decay chains of uranium (in and thorium (Th).
Energy of naturally occurring gamma radiation measurable in a borehole environment typically spans a range of about 0.1 to less than 3.0 million electron Volts (Met. The elements K, U and Th emit gamma radiation at different characteristic energies.
Components of radiation from K, U and Th contributing to the total measured gamma radiation can, therefore, be obtained by identifying these characteristic energies using spectral gamma ray logging system Through system calibration and modeling, these compo~nts can be subsequently relatcd to the cormsponding elemental concentrations of these elements within the formarion. Elemental concentrations of K, U and Th can be used to determine parameters in addition to shale content obtained from total natural gamma ray logs. These additional parameters include, but are not limited to, clay typing, lithology identification, fracture detection, and radioactive tracer placement.
As in all nuclear logging systems, statistical precision of a measurement is maximized when the count rate of the radiation detector used to obtain the measurement is maximized. Natuarally occurring gamma radiation is typically much less intense than gamma radiation induced in formation materials by sovras of radiation within a logging tool. It is important, therefore, to design natural gamma ray logging tools to maximized measured gamma radiation count rate.
Measured count rate can be optimizad by designing tool housings (both total gamma ray and spectral gamma ray) so that gamma radiation attenuation within the housing is minimized. The lower energy region of the measured spectrum is especially important in spoctral gamma ray logging systems. Wireline spectral gamma ray logging tools often employ a tool housing fabricated with material of relatively low atomic number, rather than heavier (and stronger) materials such as steel. These so called "low Z" tool cases minimize gamma ray attenuation, especially at the lower end of the energy spectrum, thereby ma~timizing measured count rate for a given radiation intensity and detector size. Low Z materials often do not meet srequirements of LWD
systems.
Measure cwnt rates can further be maximized throu~r tool detector design. Due to the relatively high energies of the characteristic K, U, and Th gamma radiation, it is advantageous for the gamma ray detector of a given type to be dimensioned as large as practically possible to react with, and thereby respond to, these radiations.
Typically, larger detectors can be disposed in wireline tools with less attenuating material between the detector and the formation. LWD systems employ a relatively thick tool housing, which is typically a cellar with a drilling fluid flow conduit passing through the char.
A gamma ray detector comprising a scintillation crystal and a cooperating light sensing device, such as a photomultiplier tube, typically Yields the highest spectral gamma ray debtor e~ciency for a given volume. Gamma ray detxtors undergo significant temp~atiut changes during a logging operation, The gain of a photomultiplier tube changes as the tempcrature and, to a lesser extent, counting rate changes. Gain changes, often referred to as gain "shifts", adversely affect gamma ray spectral analysis. Typically, a 100 degree Centigrade (°G~ change in temperat~n~e causes 10096 change in gain. Temperat<ut variations of this order of magnitude are not uuconmnon in wiirline or LWD logging operations. It is, therefore, necessary to cs'mpensate for de,Goctor gain changes in a~ to obtain accurate and pmcise spectral gamma ray measurements. This compensation is especially difficult to achieve in LWD
systems. As an example, significant gain changes can ocxvr over a relatively short time interval. The data rates of available LWD tel~r systems lxitwoen the dowahD>e tool and surface equipment are typically too low to effectively monitor and to correct for rapidly occurring gain shifts. Automatic downhole gain control is, therefore, highly desirable in LWD systems'.
As mentioned previously, naturally occurring gamma ray spectral measurements are typically low count rate. It is, therefore, desirable to use as much of the measurable gamma ray spt~um as possible in order to maximize statistical precision. Shock and vibration effects on low count rate systems can distort spectral shape, especially at the lower energy region of the measured spectrum This problem is especially prevalent in LWD systems, which an ta~posod to harsh drilling enviro~am~ents.

SLfMMARY OF T'FI>~.INVEN'rION
This present invention is dit~ected toward a spectral gamma ray logging-while-drilling (LWD) system. The system is designed to yield elemental concentrations of natwally occurring radioactive material such as K, U and Th. It should be understood, however, that the system can be used to obtain spectral measurements of any type of gamma radiation encountered in a bonehole environment.
The LWD downhole assembly or "tool" comprises a drill collar that is attached to the lower end of a drill strin.,g. A drill bit terminates tile lower end of the tool. Sensor, electronics and downhole telemet<y elements are disposed within the collar.
The tool is conveyed along a well borehole by means of the drill string, which is operated by a rotary drilling rig at the surface of the earth. Information from the tool is telem,etered to the surface via a telemetry link and received by a surface telem~etiy element contained in surface equipment that is operationally attached to the drilling rig.
Information can also be transmitted from the surface equipment to the tool via the telemetry link.
The sensor element comprises one or more gamma ray detectors that are disposed as close as practical to the periphery of the tool: This minimizes intervening material between the one or more detectors and the source of gamma radiation, which is earth formation penetrated by the borehole. As a result of this detector geometry, spectral degradation is minimized and measured count rate is maa~imi~ed for a given detector size.
The detector geometry also allows an azimuthal spectral. gamma ray measurement in a plane essentially perpendicular to the axis of the tool. The one or more gamma ray detectors preferably comprises a scintillation crystal optically coupled to a light sensitive device such as a photomultiplier tube. The detector element is calibrated under known conditions and at a "standard" detector gain. The sensor element can also contain a system, such as a magnetometer, that senses the orientation of the tool within the borehole.
Output signals from the sensor element are input to the electronics element.
The signals are amplified using appropriate preamplification and amplification circuits.
Amplified sensor signals are then input to a processor for subsequent processing. High voltage for the one or more gamma ray detectors is provided by an adjustable high voltage power supply within the electronics element. Changes in temperature or, to a lesser extent, chaages in measured gamma ray count rate result in detector gain change.
Peak sttucture location and continuum regions of measured gamma ray spectra are monitored by the processor. Any gain change is detected using predetermined relationships and criteria stored within the processor. A gain correction signal representative of the magnitude of the gain change is generated by the processor aad input to the adjustable high voltage power supply thereby adjusting detector high voltage such that the gain is restored to the standard gain. This gain control system is automatic, and requires no intervention from the surface.
With detector gain stabilized to standard gain, elemental concentrations of K, U
and Th are determined in the processor using predetermined relationships.
These elemental concentrations can be input to the dowahole telemetry element and telemetered to the surface. Alternately, gain stabilized spectral data can be input to the downhole telemetry element and telemetered to the surface for subsequent processing.
Spectral gamma ray data and elemental concentration determinations can be recorded by a data storage means within the electronics element, and subsequently extracted for processing and analysis when the tool is returned to the surface of the earth.
Elemental concentrations of K, U and Th arc determined as a function of depth as the tool is conveyed along the borehole. If a plurality of gamma ray detectors is used, the gain adjusted spectral responses of the detectors are combined to obtain the desired elemental concentrations. Preferably t1~ detector responses are combined prior to computation of ele~ntal concentrations.
The peripheral detector geometry also allows an azimuthal spectral gamma ray measurement and corresponding azimuthal elemental concentration determinations in a plane that is essentially perpendicular to the aus of the tool. Azimuthal reference is obtained by using a tool orientation sensitive device such as a magnetometer disposed within the sensor or electronics element. If a single detector is used, azimuthal measurements can be obtained only when the tool is being rotate3 by the drill string. A
plurality of detectors yields azimuthal information when the tool is rotating or "sliding"
along the borehole without rotating.

BRIEF DESCRIPT'I0,~1 OF THE DRAWINGS
So that the manner in which the above recited features, advantages aad objects the present invention are obtained and can be understood in detail, more particular description of the invention, briefly summarized above, may be had by reference to the embodiments thereof which are illustrated in the appended drawings.
Fig. 1 illustrates the spectrail natural gamma ray LWD system displayed as a whole;
Fig. 2 is a functional diagram of major elements and components of the spectral LWD system;
Fig. 3a is a cross sectional view of a spectral LWD tool sensor element comprising one gamma ray detector;
Fig. 3b is a side sectional view of the sensor element comprising one gamma ray detector;
Fig. 4 is a cross sectional view of a spectral LWD tool sensor element comprising three gamma ray detectors;
Fig. 5 is a typical gamma ray nattnal gamma ray spectrum measiu~ed with the spectral gamma ray LWD tool;
Pig. 6 shows a relationship between the slope of the Compton region of the measured gamma ray spectrum and the temperature of the gamma ray detector;
Fig. 7 illustrates relationships between detector gain adjustment factor required to obtain standard detector gain, a required high voltage adjustment to obtain standard detector gain, and detector temperature;
Fig. 8 is a more detailed view of a measured gamma ray spectrum illustrating how a spectral peak position is used to obtain a second order detector gain adjustment;
Fig. 9 is a graphical illustration of a method for locating statistically significant peak structure in a measured gamma ray specdrum;
Fig. 10 is a flow chart showing steps for automatically controlling the gain of a gamma ray detector using a measured spectral analysis method;

A$S 04-001 Fig. 11 illustrates basic concepts used for automatically controlling the gain of a gamma ray detector using a detector source gain control method;
Fig. 12 is a flow chart showing steps for automatically controlling the gain of a gamma ray detactor using the detector source gain control method;
Fig. 13 shows additional hardware components needed to obtain azimuthal natural gamma ray measurements using the LwD system;
Fig. 14 is an example of a spectral gamma ray LwD log showing concentrations of K, U and Th as a function of depth within a barehole; and Fig. 15 is an example of an azimuthal spectral gamma ray LwD log showing concentratio~s of K, U and Th as a function of azimuth anx~ad the barehole and as a function of depth within the bosehole.

Details of the preferred embodiments of the LwD spectral gamma ray logging system are p~ented in sections. System hardware is first disclosed. This is followed by disclosure of methodology used to monitor measured gamma ray spectra, and to stabilize tire gain of these spectra as basnhOle t~emnperatta~e varies. Two gain stabilization metbOds are disclosed. with both, stabilization is accoanplished in real time and without operator intervention. Once gain stabilization has been obtained, metbods for determining elemental concentrations of natiu~alty occurring K, U and Th are discussed Finally, measures of total and azimuthal concentrations of K, U and Th are discussed, and "log"
presentations of terse measm~em~ents are illustrated.
The invention is directed toward the measure of gamma radiation that oc~s naturally in earth formation. 1t should be understood, however, that the basic concxpts of the invention are applicable for quantitative measurements of any type of gamma radiation wherein one or more gamma ray deta,~tors are subject to gain shifts.
pARDwaI~
Fig. 1 illustrates the LwD system 15 displayed as a whole. A downhole assembly or "tool" uses a drill collar 10 that is ~ to the lower end of a drill string 18.

A drill bit 11 terminates the lower end of the collar 10. Within the collar 10 are disposed a sensor element 12, an electronics element 14, and a downhole telemetry 16.
The tool is conveyed along a well borehole 20, defined by borehole walls 21 and penetrating formation 22, by means of tl~ drill string 18. The drill string 18 is operated from the surface Zr4 of the earth by rotary drilling rig, which is only illustrated conceptually at 26 since such rigs are well known in the art.
Information from the tool is telemetered to the surface of the earth 24 via a telemetry link (illustrated conceptually by the arrow 23) and received by a surface telemetr3r element (not shown) contained in surface equipment 28 that is operationally connected to the drilling rig 26. Information can also be transmitted from the surface equipment 28 to the tool via the telemetry link 23.
More details of the sensor element 12, tire electronics element 14. and the downhole telemetry element 16 and their operating relationships are shown in the functional diagram of Fig. 2. The sensor elcment 12, illustrated conceptually as a broken line box, comprises at least one gamma ray detector comprising a scintillation crystal 30 and an optically coupled photomultiplier tube 32. Outpirt signals from the photomultiplier tube are input to the electronics element, whose components are enclosed by the broken line boa designated as 14. The signals are amplified using appropriate preamplification and amplification circuits 34. Amplified sensor signals are input to a processor 38. Voltage for the plmtomultiplier tube 32 is provided by an adjustable high voltage power supply 36 within the electoonics element 14.
Still referring to Fig. 2, the processor 38 provides means for automatically controlling the gain of the at least one gamma ray detector, and is also used to process signals from the gamma ray detector to obtain elemental concentrations of K, U
and Th.
As mentioned previously, the tool is preferably calibrated at the surface to a "standard"
gain. While logging, the temperature of the tool and elements therein change.
Changes in temperature or, to a lesser extent, changes in measured gamma ray count rate result in detector gain change. Gain changes are reflected in the energy spectrum of the measured detector signals. Measured features of the spectrum are used ,to correct for these gain changes, as will be discussed in detail in subsequent sections of this disclosure. A gain correction signal representative of the magnitude of the gain change is generated by the processor 38 and input to the adjustable high voltage power supply 36 thereby adjusting detector high voltage so that the gain is restored to the "standard" gain.
Elemental concentrations of K, U and Th are determined from gain corrected detector spectra in the processor 38 using predetermined relations as will be discussed subsequently.
Elcmeatal concentrations of K, U and Th are input to the downhole telemetry element 16 and telemeteted, via the telemetry link 23, to the surface telemetry t contained in surface equipment 28.
Pigs. 3a and 3b are cross sectional and side sectional views, respective, of the collar 10 in the region of the sensor element and depict a smear element comprising one gamma ray detector. Fig. 3a shows the cross section A-A' of the collar 10 with the axis of a drilling flow conduit 44 displaord from the axis of the collar. A
detector channel on the periphery of the collar 10 and defined by the surfaces 40 receives the gamma ray dadxtor compzxsing a scintillation crystal 30 each as Nal, CsI, BGO and the like. The scintillation crystal 30 is encapsulates is a hernaetically sealed, light reflecting casing 42.
The volume 46 is preferably filled with a material such RTV, epoxy and the like. The collar 10 is surrounded by a thin sleeve 48 in the region of the sensor element 12. Fig 3b shows the side section B-B' which includes the major axis of the collar 10. A
photomultiplier tube 32 is optically couplad to the scintillation crystal 30.
Blectacal leads to the photomultiplier tube are not shown for purposes of clarity.
Again referring to both I~gs 3a and 3b, it is apparent that the scintillation crystal is disposed as close as practical to the periphery of the collar 10. This minimizes intervening material between the detector and the source of gamma radiation, which is earth formation penetrated by the borehole (not shown). By displacing the axis of the flow conduit 44, the diameter, and thus the efficiency, of the detector is n~~imized. For 25 typical LVVD equipment, the diameter of the scintillation crystal can tx 2 inches (5.1 centimeters) or larger and still maintain structural specifications of the collar 10. As a result of this detector geometry, gamma ray spectral degradation is minimized and measured count rate is maximized for a given detector size.
Fig. 4 illustrates a sensor element comprising three gamma ray detectors.
'This 30 cross section view shows the scintillation crystals 30 of each detector.
Each crystal 30 is encapsulated in hermetically sealed, light reflecting casing 42, and is disposed in a detector channel defined by the surfaces 40. The channels are arranged at 120 degree angular spacings. The collar 10 is in the region of the sensor element aad is again surrounded by a thin sleeve 48. A side section view has been omitted for brevity, but a photomultiplier tube (not shown) is again optically coupled to each scintillation crystal 30. As with the single debtor sensor element shown in Figs 3a and 3b, it is apparent that the scintillation crystals 30 are disposed as close as practical to the periphery of the tool thereby minimizing intervening material between the detoaors and the source of gamma radiation within the earth formation. Using the multiple detector configurarion, the axis of the flow conduit 44 is coincident with the axis of the c~l>ar 10.
For typical LWD equipment, the diameter of each scintillation crystal is limited to about 1.5 inches (3.8 centimeters) so that structural specifications of the collar can be maintained.
Competed with the single scintillation crystal sensor element oonfigmution shown in Figs 3a and 3b, the efficiency of each datect~ on Fig. 4 is noduced. Signals from each detectoz can, however, be combined to obtain a total sensca element e~ciency that equals or exceeds the efficiency of the single detector configuration. In addition, the three de~ctm sensor element configuration offers advantages in azinmrthai speL~tral gamma ray measurements that will be discussed in a subsequent section of this disclosure.
It should be understood that the multiple detector sensor element configuration is not limited to the throe d~tar configuration shown in Fig. 4. It should also be understood that aagular spacing between the multiple detectors need not be equal.
F'mally, it should be understood that the dirneneions of the multiple dues need not be the same.
GAIN STABILIZATION
Two methods of detector gain stabilization are disclosed. The first method will be referred to as the "measured spectral analysis" method, and the second method will be referred to as the "detector source" gain correction method. The gain of an LWD gamma ray detector can change significantly and rapidly in the harsh borehole drilling environment. Telemetry links between the tool and the surface are relatively slow and do not permit gain monitoring and c~rnection from the surface. Gain control must be implemented automatically within the tool. Both of the disclosed ~thods can be used to effectively control gamma ray detector gain.
Considering the importance of gain control and the harshness of the borehole environment, it is desirable to use both methods. The two methods can be used with one serving as a primarpooethod f~ gain cal, and the second serving as a back-up method for gain control. Alternately, both methods can be used simultaneously, and the results combined to obtain a gain ca~trection. Such a combination can take a variety of forms including a simple numerical average or a weighted average.
Measured SAnalysis Method fig. 5 is a typically natural gamma ray spectrum measured in earth formation with a scintillation type gamma ray detectcu. The spectNm conoprises measured gamma ray intensity as a function of gamma ray energy, repmesented by the curve 50. The abscissa is gamma ray energy in million electron Volt (MeV), and the ordinate in the natural log of measured c:rnmt rate per inaemmzt of energy. The increments of energy are represented energy channels or "channels" on the top scale abscissa. Rep~entative peak structure from K, U and.Th is shown at energies 1.46 MeV, 1.76 MeV and 2.61 MeV, respectively.
During tool calibration, the detector high voltage is adjusted to give a detector gain for which specific energies of gamma radiation fall within dined energy channels.
This gain is referrod to as the "standard" gain. Tool catibrati~ will be discussed Earthen in a subsequent section of this disclosure.
The Compton scatter region of the spy comprises formation gamma radiation that has undergone several collisions in intGtvc~g matesiat befame it reaches the gamma ray detector. This region of the spectrum is identified by the numeral 52, and terminates at the low energy region by the "hump" 54 at energy 56. This eaponential-looking region 52 contains no direct contributions from K, U, and Tb gamma radiation.
The slope of this region is mainly a function of the photomultiplier tube gain, and can be used to monitor detector gain.
Fig. 6 is a plot of the measures of the slope of the Compton region 52 as a function of detector temperature in d~as Centigrade (°C). Measured values of slope (ordinate) versus temperature (abscissa) are indicated by the data points 62.
A curve 60 fitted through the data points 62 shows that there is essentially 1:1 correlation between the slope and detector temperature.
Curve 66 of Fig. 7 shows the relationship between a multiplicative first order gain adjustment factor Fl and coaesponding detector temperature, where (1) G.m = Fl Gau. .
G~, is the observed doctor gain, and G,,s is the previously defined "standard"
gain for which the tool is calibrated. Relationships of slope versus temperature shown graphically as cntve 60 on Fig. 6 can be combined with gain adjustment factor as a function of temper~ure s)mwn graphically as curve 66 in Fig. 7 to eliminate the temperature . This combination yields a fuactional relationship between the measured slope and the desired first order gain adjustmoat factor Fl.
At this point, high voltage can be adjusted to correct detector gain for temperature effects. Curve 68 of Pig 7 shows the relationship between required high voltage adjustmcnt to obtain G ,m and detects temper~ue. Once Fl has been obtained as descn'bed above, the high voltage Vl required to obtain G "m can then be determined. The following example is presented as a graphical solution. Assume that from a measure of the Compton slope, it has been determined that Fl = 1.1 as indicated in Fig. 7 at 70. A
horizontal line is projected until it intersects the curve 66 at a point 71. A
vertical line is projected until it intersects the curve 68 at point 72. Finally, a horizontal line is projected to the right ordinate at point 73 giving a required high voltage coa~action of +10 volts.
Referring again to Fig. 2, 10 volts added to the photomultipfier tube 32 by the adjustable high voltage power supply will adjust the gain of the gamma ray detector to the standard gain G,m.
To summarize, the relationships shown graphically in Fig. 6 and Fig. 7 are combined to develop a relationship betwecn measured slope in the Compton region as a function of high voltage required to maintain standard detector gain. The example discussed above is graphical, but it should be understood that the solution can be reduced to analytical form suitable for computation in a proccssor. A measure of slope can, thcrefore, be used to corrcct for detector gain shifts. Using this slope to pmedict gain AE.S 04-001 changes is extremely robust since it is calculated from a number of data points, it is immune to electronics noise, and it has been found that is not highly af~xted by borehole and formation conditions. A first order detector gain correction can be made for the most severe gain changes ranging from about -609b of the standard gain to +15096 of the standard gain. Such severe gain changes are ink by equally severe changes in temperature ranging from about -60 °C to about +150 °C, with 25 °C being the "standard"
calibration temperaten~e.
As discussed above, a measure of slope can be used to obtain a voltage adjustment required to obtain standard gain. This is a fast order correction considering the magnitude of gann changes that can be hand. Second and third ozder ions are made to further increase precision and accuracy of the detector gain settings. Because of these additional corrections, it is preferred not to adjust detector voltage after the fret order gain correction. Instead, the spocbrum is adjusted by adjusting the count rate per cnergy chaanel using the fret order gain cornection factor Fl. Using the previous exannple of Fi = 1.1, the width of each channel is "stretched" by 10 perceat, and the measured oouat rates are redistributed over the wider channels. This metlmdology can be thought of a "software" gain shift, and is preferably performed in processor 38. The detector gain adjustment ie now fuit>ler refined by Examining a predonninate peak in this modified energy spc~vm. Fig. 8 shows a portion of the full spoctrum 50 shown in Fig.
5, and includes a peak 80 at 1.46 MeV from K. This peak is typically the most prominent peak in the spectrum, and is suitable for the saca~ad order gain adjustment.
After modifying the spectrum using methodology previously discussed, it is observed that the maxima of the peak 80 falls in a channel Chi, at 7$. Tool calibration requires that the energy corresponding to this peak maxima fall in a modified channel Ch"m at 76, where the channels have been adjusted in width by the fret order conection Fl. The gain of the detector is finther adjusted to a second order cort~ection so that the maxima of the peak 80 falls in Ch,~. This is again accomplished with a "software" gain shift by adjusting the widths of the energy channels and redistributing the measured count rates to form a second modified spectnun. A second order gain comcction F2 is obtained from the equation Fz = (C
The gain correction process can be terminated at this point, with no further refinement of the gain setting. If this option is chosen, the con~esponding high voltage setting V2 required to obtain this second order con~cted standard gain aad is expressed math~atically as (2b) VZ = FZVi Peaks in measured gamma ray spxtra such as the curve 50 shown in Fig. 5 are identified with respect to channel (and corresponding energy) using a second deaivative algorithm after a strong filter is applied. Locations of the peaks are determined using a C~uassian fit around each peak. Fig. 9 illustrates the effectiveness of the detection and location method. Curve 86 its the socond derivative dzGdCh2 (right ordinate) of spectral count rate C as a function of corresponding energy channel Ch for a spo~ctrum of the type shown in Fig: 5. Peaks are indicated when the curve 86 cusses dzGdCh2 = 0.
Since the spectrum exbi'bits statistical variations, the curve can also exhibit a "zero crossing" due to statistics of the count raze rather than actual peak structure. It is, therefore, necessary to identify a non statistical ar "noise" zero crossings from a true zero crossing which indicate a peak. The curves 82 and 84 represent upper and lower limits of standard deviation of the count rate C as a function of energy channel, and are presented in arbitrary count rate units of the left ordinate. Only zaro crossing excursions that extend outside the standard deviation "envelope" are considered as statistically significant indications of a peak. Tyre is only one such indication in the ctnve 86 at a channel identified by the numeral 88. This corresponds to the K peak at 1.46 MeV shown clearly in Fig. 5.
It is preferred to still further refine the gain setting. Once the second modified energy spectinim has been computed, all statistically significant peaks in the second modified spectrum are located using the peak location technique discussed above. Once the energy channels in which these peaks are observed, they are compared with their corresponding "standard" channels determined in tool calibration. This methodology is similar to the single-peak methodology used for the second order gain correction, but all peaks are used in this third order correction. Channel widths are again adjusted and count rates redistributed so that all identifiable peaks fall in their corresponding standard energy channels, corrected for the first and second order software gain adjustments.
This is the third order gain correction and yields a third order gain adjustment factor F3. The unconectod detector voltage V is now adjusted to obtain a con~ected voltage V~
using the relationship (3a) Var = FlFzF3V
The corrected detector gain Gar is (3b) Gar = H V~
where H is a multiplicative constant relating the third older corrected high voltage V~ to the fully cosseted detector gain Gar. Channel widths are reset to their original values.
The measured spocbral analysis method of automatic gain conroction is swnmarized in the flow chart shown in Fig. 10. The slope of the Campton region 52 (see Fig. S) is aoessured at 90. The first a~rd~er gain c~n~ection Fl is determined at 92 using the measured slope as discussed above. An identifiable peak is located in the measured apectinm at 94. The sxond order gain c~ae~ion PZ is determined at 9b using previously discussed methodology and equation (2a). All statistically significant peaks in the measured gannma ray spectrum are determined at 98. The third order gain ~tion factaar F3 is obtained at 100 by a software gain adjustment that positions all peaks in align~o~ent with their assigned energy channels obtained at tool calibration.
The corresponding high voltage V,~ requirad for standard detector gain is also deternnined at 100 using equation (3a). Tlnr corrected detector gain Gar is set at 102 using V3 and equation (3b). It again noted that an actual voltage adjustment is made only after the third order cort~action, with software gain adjustments being used in the first and second order corrections. It should also be understood that other algronithms can be used to obtain suitable software gain adjustments for the first and second order corrections.

Gamma ray detector gain can be monitored using as alternate technique. A small radioactive "detector" source is disposed near or within the one or mom scintillation crystals comprising the aatural gamma ray LWD sensor element. The detector source generates a "calibration" peak in the measured gamma ray spectrum. If the gain of the measured spectrum changes, the position of the calibration peak shifts with the change in gain. A measure of position of the calibration peak caa, therefore, be used to monitor and to correct detectoar gain.
The calibration peak is preferably at a relatively low energy so that it will not interfere with higher energy radiation from K, U and Th used to determine elemental concentrations. A suitable source is Ameriaum 241 (ulAm) which emits gamma radiation at 0.060 MeV. Referring again to Fig. 5, a typical measured natural gamma ray spectrum passes an energy range of 0.0 to 3.0 MeV over typically 256 channels. With this "standard" detector gain setting, the low energy end of the spectrum, which includes the 0.060 MeV calibration peak, is very susceptible to elecrr~ics noise.
In addition, since the spec~am spreads over about 3.0 MeV and typically 256 energy channels, the ~lAm peak occupies only about 3 out the 256 channels, which makes it di~cult to pmcisely locate the peak p~ition.
Attention is directed to Fig. 11, which conceptually depicts the low energy region of a gamma ray spoctruna measured with a da~cbor comprising a ~lAm smncx.
The curve 110 shows the peak structure with the detector set at standard gain.
Since the peak occupies only three energy channels, it is di~cult to locate the center of the peak using previously discussed methods. This peak can, in principle, be used as shown to stabilize detector gain. Any gain stabilization using the ~lAm peak at 0.060 MeV would, therefore, be subject to large ensors, especially at the higher energy region of the spectrum used for elemental concentration calculations.
The precision of detector gain stabilization using a low energy detector so~nce and calibration peak is improved using dual gain circuitry. The spectrum signal from the gamma ray detector is "branched" and input into first and second amplification circuits connprising the dual gain circuitry. The first circuit comprises a standard amplification circuit and generates a spectrum with standard gain. The 0.060 MeV ?''lAm peat in this standard spoct<um is shown at 110 in F'ig. 11. For purposes of gain stabilization, the spectrum signal is input to a second amplification circuit with a gain factor of N greater than that of the standard gain. The second amplification circuit generates as amplified spectrum with as "amplified" gain. For purposes of discussion, it will be assumed that N
= 10, although it should be understood that other values of N can be used.
Curve 112 is the amplified gain spectrum showing the ~~Am peak at 0.060 MeV fed by a factor of N = 10. The peak now occupies about 30 energy channels, and previously discussed peak location m~cthoda are used to deterrmine that the center of the peak is in energy channel P~", which identified at 114. From tool calibration, it is known that energy 0.060 MeV should fall in energy channel P,m for the standard gain, or in channel N a P,m for the amplified gain, shown at 116 in Fig. 11. The detector high voltage V
is adjusted to a casrected value, V~ using the relationship (4) Var = V (N P,,d/P"b,) .
A signal pmpartional to (N P"~/P~ is preferably generated in the processor 38 and input to the adjustable high voltage power supply 36. This generates the corrected high voltage V~ supplied to the detector. C:ornocted standard gain amplification G~ is expmessed by the relationship (5) G~ = H V~
where H, as in equation (3), is a multiplicative constant relating high voltage to detector gain.
Tt should be understood that various methods can be used to increase the detector gain by a factor of N. As an example, the amplification circuit 34 (see Fig.
2) can contain a high gain element which, under the control of the processor 38, 'branches"
detector input. The gain of one branch of the input by a factor on N thereby forming the amplified gain of the calibration peak for purposes of calibration source gain stabilization.

The gain stabilization method using a radioactive "detector" source is summarized in the flow chart of Fig. 12. The low energy portion of the measured gamma ray spectnim is increased by a factor of N at 120. The energy channel Pte, in which the stabilization peak is maximum, is determiturd at 122 using a suitable peak location technique. High voltage V~ required to position the peak maxima in energy channel N a P~ is determined (see equation (4)) at 124, and the correct detector gain G~
is set at 126 (~ ~ (5)).
~i~ nrb ~a Correction Method The measured spa~ral aaalysis method a~ the detocto~ sourx gain cornxtion methods can be combined to yield a hybrid gain control method. A calibration som~ce is disposed in within oar in the immediate vicinity of at least one gamma ray detector. When in the bamehole, this dad produces a gamma ray spectrum comprising a first component from nahually occurring radioactive elements within the formation aad a second component from the calibration source. A first detxtor gain correction is determined from spectral feature from the naturally occurring gamma radiation as previously discussed in the measured spectral analysis metbod. A second gain correction is dete mined firm the cafbrati~ source component as previously discussed in the detector source gain connection method. The first and second gain corrections are combined to coaect for gain shift of the. detector.
EZ~~NTAL CONCENTRATION DETERMINATIONS
With detector gain stabilized to "standard" gain, elemental concentrations of K, U
and Th are determined, preferably in the processor 38 of the electronics element 14 (see Figs. 1 and 2), from measured spectretl data. These elemental concentrations can be input to the downhole telemetrsr element 16 and telemeta~ed via the telemetry link 23 to the surface equipment 28. Alternately, the spectral data can be input to the dowahole telemetry. element 16 and telemetered to the surface equipment 28 for subsequent processing. Since the telemetry bandwidth is limited and the gamma ray spectra are much more data intensive than the elemental concentrations determined therefrom, it is preferned to telemeter the elemental concentrations of K, U and Th to the surface.
Alternately, spectral gamma ray data and elemental concentration determinations can be recorded by a data storage means within the electronics element, and subsequently extracted from procxssing and analysis when the tool is red to the surface.
S The following methodology is preferred for determining elemental concentrations of K, U and Th. It should tx understood, however, that other spectral processing methods such as spectrum stripping, peak area analysis and the like can be used to deternnine concentrations of K, U and Th. The required elemental concentration calibration constants are obtained at tool calibration.
Elemental concentrations are obtained by solving tlar matrix equation [Cl _ [Al IMl -[C] is a m x 1 coh~mn matrix comprising elements c~ (i = 1, ..., m) representing crnmt rate in energy channel i (see leg. 5). Typically 256 energy channels (m =
256) are used, although mrnre or fewer channels can be used within the scope of the invention.
[A] is a m a j matrix comprising elements a~ with (i =1, ..., m) and (j = K, U, Th).
Physically, the element a~ is the sensitivity of energy channel i to the element j, typically in units of counts per second p~ part per million (U and Th) or counts per second per percent (I~. The matrix [A] comprises calibration constants, is referred to as a "sensitivity" matrix, and is determined at tool calibration. At tool calibration, the response of the tool is measured in fa~ati~s coataini~og known concentrations of K, U
and Th, and in "standard" borehole conditions, and with the one or more detectors in the sensor element operated at "standard" gain G~.
[Mj is a j x 1 column matrix comprising elements Mj (j = K, U, Th) which are the parameters of interest, namely the formarion elemental concxatrations of K, U
and Th.
Mg is in percent, and MU and M~, in parts per million (ppm). The desired elemental concentrations are obtained by solving eqaation (6) for (M), preferably using a weighted least squares fit.

Measured gamma ray spectra from one ~ more gamma ray detectors in the sensor section are track~i as a function of depth of the tool in the borehole 20 (see Fig. 1). If the sensor element 12 comprises only one gamma ray detector as shown in Figs. 3a and 3b, the elements of the matrix [C] are obtained from that detector. If the sensor element comprised a plurality q of detectors, such as the q = 3 embodiment shown in Fig. 4, the elements of the [C] matirix are obtained by combining responses of the q detectors, Y bY ~Y summing the responses if all d~ectoZ'8 exhibit equal sensitivity.
AZIMU'IxAL EZ~NTAL CONCBN'I~tATION DETBRMiNATIONS
The spectral gamma ray LRTD system can be used to measure elemental concentrations Mg, MU and M~ as a function of azimuth within the borehole as well as a function of depth within the borohole. Azimuthal measurements require additional components disposed pmccferably within the electronics element 14. Fig. 13 is a functional diagram of components added to the electronics element shown in Fig. 2 so that azimuxhal elemental concentrations Mg, MU and M~, can be determined. A device sensing tool orientation, such as a magneGam~et~ 130, and a clock 132 are operationally connected to the processor 38. As in the previous discussion of Fig. 2, signals fmm the one or more gamma ray detcctoars and amplifier circuits are input to the procxssor at 136.
The processor 38 again controls detector gain adjustments of the detectors at 138 thmugh the adjustable high voltage power supply 36. Spe~al and elemental concentrations are output from the processor at 134 as described below.
As the tool rotates through 360 degrees, gamma ray spectra of the form shown in Fig. 5 are measured during discrete time intervals fit, where these elements are defined by the clock 132 cooperating with the processor 38. Spectra are stored in bins according to time intervals ~t in which they are measured. The time interval At is preferably about 50 milliseconds. During each time interval, the average reading of the magnetometer 130 is determined thereby defining an azimuth sector associated with each time interval, and thereby assigned an azimuth sector to each bin. Each bin, therefore, contains a gamma ray spectrum measured at a known borehole azimuth sector. The spectral data binning, and the averaging of magnetometer readings during each time interval, are controlled by AES 04.001 the processor 38. Binned spectral data and corresponding azimuth sectors are preferably stored in the processor 38. The process is repeated through multiple 360 degree rotations within a given depth interval dd in order to maximize statistical precision of each natural gamma ray spectrum stoned in each bin. Gain stabilization techniques previously disclosed in detail are used to control the gain of each binned spectzunn.
Previously discussed data analysis methods are used to compute the matrix [M] for each binned Y Yi~~ ~ eons Mg, MU and M~ for each azimuth sector around the borehole.
If the sensa~r element comprises a plurality of detectors, detector outputs are phased by the processor 38 so that as each detector mtates through each azimuth sector, output from that detector is stored within the bin corresponding to that azimuth sector.
The tool can be conveyed along the barehOle without rotating. This conveyance is commonly refen~ed to as "sliding". If the sensor element 12 comprises only one gamma ray detcctar, azimuthal nahnnl gamma ray spactral measurements can not be made when the tool is sliding. If the sensor element comprises a plurality of gamma ray d~ectats, azimuthal spectral measurements can be obtained while sliding. The magnitudes of the azimuth sectors are determined by the number of detectors in the sensor element. For the sensor element comprising three deteL~tors on 120 degree centers as shown in Fig, 4, each azimath sector would be 120 degc~ees. This yields an azimuthal resolution that is typically inferior to that obtained with the tool rotating and with time intervals ~t of about 50 milvseconds.
LOG PRBSENTATIONS
Pig. 14 shows an example 140 of a natural gamma ray LSD log presentation of MR, MU and M~, as a~ function of depth in the borehole. The quantities Mg, MU
and M~
are computed from measured spectrral data [C] using equation (6). Units for concentrations of K (~), U (ppm) and Th (ppm) are shown in the fields 141, 143 and 145, respectively. Scales are typically in qb per chart division for K and ppm per chart division for U and Th. Concentrations of Ma, MU and M~ are shown as a function of depth 148 in the borehole by curves 142, 144 and 146, respectively. As an example, excursions 147 and 149 in Mx and MU, respectively, are indicated at a depth of about xR20. An excursion 159 in M~ is indicated at a depth of about xx40. It should be understood that other formats can be used to present the basic LWD natural gamma ray log data.
Fig. 15 shows an example 150 of an azimuthal natural gamma ray LWD log presentation. Elemental concentrations of Mg (96), My (ppm) and M~ (ppm) are designated with solid, long dashed and short dashed curves 164, 162, and 160, respectively, as shown in field 151. Corresponding scales for these concentrations are tabulated in field 1 SO and are typically in °6 per chart division for Mg and ppm per chart division for MU and M~,. Concentrations Mg, Mu and M~, obtained from spectra summed over a depth interval ed. shown in the field 153, are shown as a function of azimuth sector 152, in degrees, for that depth interval. As an example, excursions 156 ~d 154 in Mg and MU, respectively, are sha~wn at an azimuth sector of about 180 degc~ees over the depth interval xx20. As another example, as excursion 158 in M~ is shown at an azimuth sector of about 225 degrees over the depth interval ~u40. It should be understood that other formats can be used to present the basic LWD azimutbal natural gamma ray log data.
While the foregoing disclosure is directed toward the preferned embodiments of the invention, the scope of the invention is def ned by the claims, which follow.

Claims (56)

1. A gamma ray logging while-dulling system comprising:
(a) at least one gamma ray detector that measures a gamma ray energy spectrum; wherein (b) a first adjustment of gain of said detector is made using a measure of slope of a Compton scatter region of said spectrum.
2. The system of claim 1 wherein a second adjustment of said gain is made by:
(a) measuring the location of an energy peak in said spectrum; and (b) adjusting said gain so that said location corresponds to a standard location for said energy peak.
3. The system of claim 2 wherein a third adjustment of said gain is made by:
(a) measuring locations of a plurality of energy peaks in said spectrum;
(b) adjusting said gain so that each said location of each of said plurality of peaks corresponds to a standard location for that peak.
4. The system of claim 3 further comprising a processor cooperating with said at least one detector, wherein:
(a) said spectrum comprises gamma ray count rate rid as a function of energy channel within said processor, and (b) said first adjustment comprises adjusting, within said processor, width of said energy channels as a function of said measure of slope.
5. The system of claim 4 wherein said second adjustment comprises adjusting, within said processor, said width of said energy channels so that said location of said energy peak corresponds to a standard location for said energy peak.
6. The system of claim 5 further comprising an adjustable high voltage power supply cooperating with said processor and said at least one detector, wherein said third adjustment comprises adjusting high voltage supplied to said at least one detector thereby setting said gain of said at least one detector to a standard gain.
7. The system of claim 1 further comprising a collar, wherein said at least one detector is disposed in a detector channel at the periphery of said collar.
8. The system of claim 1 further comprising a collar, wherein two or more detectors are each disposed within detector channels angularly spaced around the periphery of said collar.
9. The system of claim 6 wherein:
(a) said spectrum comprises gamma radiation from at least one naturally occurring radioactive element in formation penetrated by a borehole; and (b) said spectrum is combined with calibration constants in said processor using a predetermined relationship to obtain an elemental concentration of said at least one naturally occurring radioactive element.
10. The system of claim 9 wherein said at least one elemental concentration is measured as a function of depth within said borehole.
11. The system of claim 9 wherein said at least one elemental concentration is measured as a function of azimuthal sector around said borehole.
12. The system of claim 9 wherein said naturally occurring radioactive elements comprise potassium, uranium and thorium
13. A gamma ray logging-while-driving system comprising:
(a) At least one gamma ray detector that measures a gamma ray energy (b) a calibration source disposed near or within said at least one detector and emitting calibration radiation; and (c) dual gain circuitry comprising a standard amplification circuit and a high gain circuit; wherein (d) said spectrum is branched and input into said dual gain circuitry producing a standard gain spectrum and an amplified gain spectrum;
(e) in said amplified gain spectrum, the observed position of a calibration peak from said calibration radiation is compared with a predetermined standard position for said calibration peak; and (f) results of said comparison are used to connect said standard gain spectrum to a standard detector gain.
14 The system of claim 13 further comprising:
(a) an adjustably high voltage power supply cooperating with said at least one detector; and (b) a processor cooperating with said dual gain circuitry and said adjustable high voltage power supply; wherein (i) said comparison is made in said processor, (ii) said processor generates a calibration signal indicative of said comparison and inputs the said calibration signal to said adjustable high voltage power supply, and (iii) high voltage supplied to said at least one detector by said adjustable high voltage power supply is adjusted in relation to said calibration signal thereby connecting said standard gain spectrum to said standard detector gain.
15. The system of claim 13 further comprising a collar, wherein said at least one detector is disposed in a detector channel at the periphery of said collar.
16. The system of claim 13 further comprising a collar, wherein two or more detectors are each disposed within detector channels that are angularly spaced around the periphery of said collar.
17. The system of claim 14 wherein:

(a) said spectrum comprises gamma radiation from at least one naturally occurring radioactive element in formation penetrated by a borehole; and (b) said spectrum is combined with calibration constants in said processor using a predetermined relationship to obtain an elemental concentration of said at least one naturally occurring radioactive element.
18. The system of claim 17 wherein said at least one elemental concentration is obtained as a function of depth within said borehole.
19. The system of claim 17 wherein said at least one elemental concentration is obtained as a function of azimuthal sector around said borehole.
20. The system of claim 17 wherein said spectrum comprises gamma radiation from potassium, uranium and thorium.
21. A method for measuring gamma radiation while drilling a borehole, the method comprising the steps of:
(a) measuring a gamma ray spectrum with at least one gamma ray detector:
and (b) making a first adjustment of gain of said detector using a measure of slope of a Compton scatter region of said spectrum.
22. The method of claim 21 comprising the additional step of making a second adjustment of said gain by:
(a) measuring the location of an energy peak in said spectrum; and (b) adjusting said gain so that said location corresponds to a standard location for said energy peak.
23. The method of claim 22 comprising the additional step of making a third adjustment of said gain by:
(a) measuring locations of a plurality of energy peaks in said spectrum; and (b) adjusting said gain so that each said location of each of said plurality of peaks corresponds to a standard location for that peak.
24. The method of claim 23 comprising the additional steps of:
(a) operationally connecting a processor to said at least one detector;
(b) obtaining with said processor said spectrum comprising gamma ray count rate as a function of energy channels; and (c) making said first adjustment of said gain, within said processor, by adjusting width of said energy channels as a function of said measure of slope.
25. The method of claim 24 comprising the additional step of making said second adjustment of said gain, within said processor, by adjusting said width of said energy channels.
26. The method of claim 25 comprising the additional steps of:
(a) providing an adjustable high voltage power supply which cooperates with said processor and with said at least one detector; and (b) making said third adjustment of said gain by adjusting said adjustable high voltage power supply thereby setting said gain of said at least one detector to a standard gain.
27. The method of claim 21 comprising the additional step of disposing said at least one detector in a detector channel at the periphery of a collar.
28. The method of claim 21 comprising the additional steps of disposing two or more detectors each within detector channels that are angularly spaced around the periphery of a collar.
29. The method of claim 26 comprising the additional steps of:
(a) measuring said spectrum comprising gamma radiation from at least one naturally occurring radioactive element in formation penetrated by said borehole; and (b) combining said spectrum with calibration constants in said processor using a predetermined relationship to obtain an elemental concentration of said at least one naturally occurring radioactive element.
30. The method of claim 29 comprising the additional step of obtaining said at least one elemental concentration as a function of depth within said borehole.
31. The method of claim 29 comprising the additional step of obtaining said at least one elemental concentration as a function of azimuthal sector around said borehole.
32. The method of claim 29 wherein sand spectrum comprises gamma radiation from potassium, uranium and thorium.
33. A method for measuring gamma radiation while drilling a borehole, the method comprising steps of:
(a) measuring a gamma ray energy spectrum with least one gamma ray detector;
(b) disposing a calibration source near or within said at least one detector;
(c) measuring within said gamma ray energy spectrum calibration radiation emitted by said calibration source;
(d) providing a dual gain circuitry comprising a standard amplification circuit and a high gain circuit;
(e) breaching said spectrum into said dual gain circuitry thereby producing a standard gain spectrum and an amplified gain spectrum;
(f) in said amplified gain spectrum, observing a position of a calibration peak resulting from said calibration radiation;
(g) comparing said observed position with a predetermined standard position for said calibration peak; and (h) using said comparison to correct said standard gain spectrum to a standard detector gain.
34 The method of claim 33 further comprising the additional steps of:
(a) providing an adjustable high voltage power supply which cooperates with said at least one detector; and (b) providing a processor that cooperates with said dual gain circuitry and said adjustable high voltage power supply;
(c) making said comparison in said processor;
(d) generating a calibration signal indicative of said comparison;
(e) imputing said calibration signal to said adjustable high voltage power supply; and (f) adjusting high voltage supplied to said at least one detector by said adjustable high voltage power supply in relation to said calibration signal thereby correcting said standard gain spectrum to said standard detector gain.
35. The method of claim 33 comprising the additional step of disposing said at least one detector in a deb channel at the periphery of a collar.
36. The method of claim 33 comprising the additional step of disposing two or more dues each within detector channels that angularly spaced around the periphery of a collar.
37. The method of claim 34 comprising the additional steps of:
(a) measuring said spectrum comprising gamma radiation from at least one naturally occurring radioactive element in formation penetrated by a borehole;
and (b) combining said spectrum with calibration constants in said processor using a predetermined relationship to obtain an elemental concentration of said at least one naturally occurring radioactive element.
38. The method of claim 37 comprising the additional step of obtaining said at least one elemental concentration as a function of depth within said borehole.
39. The method of claim 37 comprising the additional step of obtaining said at least one elemental concentration as a function of azimuthal sector around said borehole.
40. The method of claim 37 wherein said spectrum comprises gamma radiation from potassium, uranium and thorium.
41. A gamma radiation logging-while-drilling system for measuring elemental concentration of at least one naturally occurring radioactive element in a formation penetrated by a borehole, the system comprising:
(a) at least one gamma ray detector; and (b) a calibration source in the vicinity of said at least one gamma ray detector;
wherein (c) said gamma ray detector measures a gamma ray spectrum comprising a first component from said at least one naturally occurring radioactive element and a second component from said calibration source;
(d) a first detector gain correction is determined from features of said first component;
(e) a second detector gain correction is determined from said second component; and (f) said first and said second gain corrections are combined to correct for gain shifts in said gamma ray detector.
42. The system of claim 41 further comprising a processor, wherein features of said first component ate combined with calibration constants in said processor using a predetermined relationship to obtain said elemental concentration of said at least one naturally occurring radioactive element.
43. The system of claim 42 wherein said at least one elemental concentration is obtained as a function of depth within said borehole.
44. The system of claim 42 wherein said at least one elemental concentration is obtained as a function of azimuthal sector around said borehole.
45. A method for measuring, while drilling a borehole, elemental concentration of at least one naturally occurring radioactive element contained in formation penetrated by said borehole, the method comprising the steps of:
(a) conveying at least one gamma ray deb within said borehole;
(b) disposing a calibration source in the vicinity of said at least one gamma ray detector;
(c) measuring, with said at least one gamma ray detector, a gamma ray spectrum comprising a first component from said at least one naturally occurring radioactive element and a second component from said calibration source;
(d) determining a first detector gain correction from features of said first component;
(e) determining a second detector gain correction from said second component; and (f) combining said first and said second data gain corrections to correct for gain shifts in said at least one gamma ray detector.
46. The method of claim 45 comprising the additional step of combining features of said first component with calibration constants using a predetermined relationship to obtain said elemental concentration of said at least one naturally occurring radioactive element.
47. The method of claim 46 comprising the additional step of obtaining said at least one elemental concentration as a function of depth within said borehole.
48. The method of claim 46 comprising the additional step of obtaining said at least one elemental concentration as a function of azimuthal sector around said borehole.
49. A gamma ray logging-while-drilling system comprising:

(a) at least one gamma ray detector, and (b) a processor operationally connected to said at least one detector; wherein (c) said gamma ray detector cooperates with said processor to yield a spectrum comprises gamma ray count rate recorded as a function of energy channel.
50. The system of claim 49 further comprising a collar, wherein said at least one detector is disposed in a detector channel at the periphery of said collar.
51. The system of claim 49 further comprising a collar, wherein two or more detectors are each disposed within detector channels angularly spaced around the periphery of said collar.
52. The system of claim 49 wherein:
(a) said spectrum comprises gamma radiation from at least one naturally occurring radioactive element in formation penetrated by a borehole; and (b) said spectrum is combined with calibration constants in said processor using a predetermined relationship to obtain as elemental concentration of said at least one naturally occurring radioactive element.
53. A method for measuring gamma radiation while drilling a borehole, the method comprising the steps of:
(a) disposing at least one gamma ray detector within said borehole;
(b) operationally connecting a processor to said at least one detector; and (c) with said processor cooperating with said at least one gamma ray detector, measuring an energy spectrum of said gamma radiation comprising gamma ray count rate recorded as a function of energy channel.
54. The method of claim 53 comprising the additional step of disposing said at least one detector in a detector channel at the periphery of a collar.
55. The method of claim 53 comprising the additional step of disposing two or more detectors within detector channels angularly spaced around the periphery of a collar.
56. 'The method. of claim 53 wherein:
(a) said spectrum comprises gamma radiation from at least one naturally occurring radioactive element in formation penetrated by a borehole; and (b) said spectrum is combined with calibration constants in said processor using a predetermined relationship to obtain an elemental concentration of said at least one naturally occurring radioactive element.
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US7253401B2 (en) 2007-08-07
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US20050199794A1 (en) 2005-09-15
CA2497355C (en) 2015-10-27

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