• 专利附录
  • 专利说明
  • 权利要求
  • 类似技术
  • 同族专利
  • 引用文献
  • 法律状态
  • 优先权
    • 专利摘要:
    1470568 Borehole logging SCHLUMBERGER Ltd 1 May 1974 [1 May 1973] 19104/74 Heading G1A The invention relates to verifying the accuracy of borehole logging measurements obtained by irradiating the formation with pulsed neutrons and monitoring, thermal, neutron populations in the formation by means of two detectors spaced at different distances along the logging tool from the neutron source. The method used involves obtaining a value of a thermal neutron absorption characteristic e.g. the decay time # N for the "rear" detector and using this with signals derived from the "far" detector, to obtain a ratio representative of or from which is derivable the quantity # N /# F ; this ratio should equal unity for valid measurements and deviation therefrom indicates the effects of neutron diffusion &c. on measurement accuracy. The logging tool comprises sodium iodide scintillation crystals coupled to photo-multiplier, monitoring γ-radiation from thermal neutron capture or alternatively, thermal neutron sensitive detectors e.g. He-3 filled proportional counters. The neutron source 18 is arranged to produce discrete pulses of 14 Mev high energy neutrons of one decay time (#) duration, at intervals of 12-15#. The neutron population is sampled in these intervals at 2# after the irradiation pulse has ended for a duration of #: at 3# afterwards for 2# duration; and at 11# afterwards for 3# duration. The first and second sample periods counts; N 1 , F 1 and N 2 , F 2 , represent neutron population counts and the third N3, F 3 , represent background gamma counts to be subtracted therefrom. In the arrangement of Fig. 1, # N and # F are calculated by loops 26, 28 which operate by adjustment of the sample interval times and durations until a predetermined value for ratios N 1 /N 2 and F 1 /F 2 are obtained, when the first sample interval duration will equal # N , # F respectively. Values of # N , or # N /# F are recorded on tape and visually. In the embodiment of Fig. 2 (not shown), only a # N loop is provided, the # F loop being replaced by a far signal gating circuit controlled by the # N loop. The function used to test accuracy in this case is the ratio F 1 /F 2 which is linearily related to # N /# F . # N and the ratio # N /# F obtained from F 1 /F 2 by means of a potentiometer, are recorded. Alternatively, they are supplied to a circuit, Fig. 4 (not shown) which averages # N /# F and under it by # N to obtain # F also. In a further alternative, Fig. 5 (not shown) # N /# F is compared with a reference value to select whether # N or # F is recorded as the more accurate. In a further embodiment, a computer is used to solve an exponential equation relating the far detector counting rate ratio and # N , Fig. 6 (not shown).
    公开号:SU847948A3
    申请号:SU742026858
    申请日:1974-04-30
    公开日:1981-07-15
    发明作者:В.Джонстоун Чарльз
    申请人:Шлюмбергер Оверсиз С.А. (Фирма)；
    IPC主号:
    专利说明:

    various points of the formation surrounding the well. The measurement period is chosen so as to reduce the effects of the liquid, and the density of thermal neutrons decreases exponentially. The measured neutron lifetime toti) (gle &) thus corresponds to the apparent constant lifetime of the neutrons in the earth formation surrounding the well. Consequently, devices for measuring the intrinsic neutron characteristic of the earth formation have low sensitivity and accuracy, since it is not possible to measure with sufficient accuracy the neutron source density at two remote points of the earth formation. The closest technically to the proposed is a device for measuring the intrinsic neutron characteristics of an earth layer containing a pulsed neutron radiation source, hermetically sealed in a housing, the first and second radiation detectors located at different distances from the neutron radiation source, the first and second signal processing units, each of which is connected to one of the radiation detectors, a signal ratio unit, a switch, a recorder, etc., than one of the processing units OIT from the circuit having a timing circuit upravlani. In the device, the measurements are carried out for periods of time between neutron pulses. The recorded values allow to obtain the neutron characteristic of the earth layer, i.e. visible constant of the time of Crstr. slowing down or life of thermal neutrons. The value (visible) or (measured) corresponding to each change in neutron density is then stored in the memory. The ratio of the two is the value characterizing the degree of correspondence of the two measured values. If the measured Cfrvg g values are close to each other, i.e. Z / t approaches unity, one or both of these quantities can be used to accurately measure the true value of the Neutron density (thermal neutrons) at a point measured for two limited time intervals between neutron pulses, and the ratio of neutron magnitudes is determined. densities. The intervals are chosen so that the ratio is equal to the specified number. The selection of time intervals is carried out in such a way that the duration of one of the intervals provides a measurement corresponding to the measurement of the neutron density at this point. The intervals of measurements at the second point following each successive neutron pulse are equal to specified intervals of time corresponding to the measurements at the first point, and the ratio of the measured neutron densities at the second point during the first and second specified time intervals is compared with each other or with a given equivalent. If this second ratio closely approximates this equivalent, then the predetermined value of the thermal neutron deceleration time, measured at the first point, can be used to accurately determine C. If the specified second neutron density ratio to a sufficiently high degree of approximation is associated with a linear relationship with the CC / tfj ratio, obtained by observing T at the first and second points, then it can be converted to j / i. This good convergence is observed when t. / tr from each other o / tij are equal to one, the correct tg T or) value can be obtained by using C) / Cj to determine or an accurate measurement of the true neutron characteristic value can be obtained by directly solving the exponential function with respect to measurement data and characteristics neutron density. Thus, the known device has low accuracy. The circuit of the invention is an increase in measurement accuracy. This goal is achieved by the fact that, in a device for measuring the intrinsic neutron characteristic of an earth formation containing a pulsed neutron radiation source, the first and second radiation detectors hermetically closed in a housing, located at different distances from the neutron radiation source, the first and second signal processing units, each of which is connected to one of the radiation detectors, a signal ratio unit, a register switch, and one of the processing units consists of a circuit L. having a control circuit In this case, a selector is connected to the second processing unit, connected to the synchronization control circuit and an analog unit, the output of the selector being connected to the input of the analog unit, the output of which is connected to the input of the recorder. The analog block is designed as a divider. FIG. 1 shows a block diagram of a device for measuring the intrinsic neutron characteristic of a zeine formation j in FIG. 2, a second variant of the proposed device for obtaining reliable optical measurement of neutron radiation parameters; in fig. 3 - rake, showing a correlation with the ratio TDGN to the ratio of the count rate N; (set of true values) / 2C (set of true values) for the optimal sequence of triggering of the detector in FIG. 4 is a block diagram for recording the value of b and entering the system shown in FIG. 2; Fig. 5 is a block diagram for the automatic sampling and recording of the Ltz value, through which the true parameter ,, can be accurately determined. The device for measuring the intrinsic neutron characteristic of the earth layer contains a sealed durable capsule (or depth device) 1 that is in a suspended state NII in the well 2, IC, replenished casings of pipes. The deep 1st device i is held by cable 3 and is designed to investigate the properties of the earth layer 4 adjacent to the well. Capsule i contains a pulsed electron source 5 and two detector 6 and 7 separated by a given distance. Neutron source 5 generates discrete pulses of high energy neutrons (14 MeV). The radiation detectors 6 and 7 measure the thermal neutron densities in the formation 4, which are proportional to their removal in which the neutron detections from the neutron source are located. Signals representing fj gj
    权利要求:
    Claims (2)
    [1]
    As detectors 6 and 7 can correspond to the measurement, the detectors of thermal neutrons of the neutron flux at the near 48b tron, weakened, i.e. Non-proportional counters, or radiation detectors; those. scintilpors on Naf-crystals that react to - radiation arising from the radiation capture of thermal neutrons by the cores of the elements of the earth formation under study. In this case, it is assumed that the detectors 6 and 7 are radiation detectors based on sodium iodide crystals. The radiation detectors are located relative to the neutron source 5 in the upper part of the capsule. Near. from source 5, detector 6 should be placed so that the center of its scintillation crystal (not shown) is located 36.83 cm from the target (not shown) of the neutron source 5. The scintillation crystal can be about 10.16 cm long and may be optically coupled to the photomultiplier. The geometrical center of the SSCNTILLY 1910NOGO Kristach1a detector 7, located at a large distance from the neutron source 5, is located approximately at a distance of 63.5 cm from the target of the neutron source. It is also optically coupled to a photomultiplier. In the capsule I, there are an amplifier and a discriminator for suppressing DIFFERENTILE interference, which are not related to the nuclear processes recorded in the capsule, the processing units 8 of the intended informantin can be located completely on the surface of the component. Another portion of the blocks may be in a capsule. 8 consists of a block 9 located in a well, and a block 10 located 1 cent on the surface of the earth. The underground unit 9 includes two units 11 and 12 of processing the output information ESC, connected by means of conductors 13 and 14 with the proximal 6 and distant 7 detectors, respectively. The blocks It and 12 are triggered on the basis of the corresponding 10SH1X radiation detectors 6 and 7. These blocks generate signals proportional to the apparent values of t, which correspond to the rates of reduction of the potential of thermal neutrons at two points, the detector, at-meoa (tp), correspond to the measurement of the attenuation of the neutron flux at the far detector. These signals are sent to the master block 15, through which the measured information on leads 16 and 17 is fed to the processing block 10 of the measured formation. The signals tfj and T / p are fed to the analog dividing unit 18, on which the signal corresponding to the ratio t is formed. One or both of the signals of the Htp TC, together with the output signal of the 6jiOKa 18 division, which corresponds to the ratio tTj / tp, can be transmitted to the recording device 19. The T / c signal is usually recorded as C, since it has a higher statistical accuracy. However, under certain circumstances, tp more closely approximates the true value of Tj than tj. In these cases, it is preferable to register the p instead of ffj, for which the recording device 19 has a selector switch 20. The recording device 19 co (the tape recorder’s recording device and the visual perception of information. The operation of the neutron source 5 is determined depending on the the values of tr) Tj-e. the duration of individual neutron pulses and the time between successive pulses is proportional to 1 / | „d5 Block 11 - tjj is connected by conductor 21 to a neutron source 5, while the output signals from block 11 trigger a neutron source 5, which emits neutron pulses, the duration and frequency of which depend on value. In the case of non-divergence, block 12 may be used to control the operation of the neutron source 5, in which case conductor 21 (22) must pass to this block. In any case, only one of the two t-blocks controls the operation of the neutron source 5. The block f generates a synchronized signal relative to the end of each neutron pulse, which is necessary for proper time control by the detection intervals associated with the t-block. This signal can be received from the T-block controlling the operation of the neutron source 8 via conductors 27 (from the tN-block 11 to the tp-block 12). More accurate results are obtained by controlling the frequency and duration of the neutron pulses of a block; however, this control is not necessary; instead, pulses of constant duration, which occur at constant intervals in time, can be used. In this case, the Cr-block can be on the surface and can be synchronized from the common signal coming from the depth instrument (not shown) and the corresponding end of each neutron pulse. If it is necessary to control the neutron source depending on the E., it can be carried out when one or both C-boxes are at the top. The device works as follows. Block 11 generates a signal corresponding to the rate of attenuation (absorption) of the thermal neutron flux in the formation by means of a near detector 6. The preferred measurement sequence is the mode in which successive neutron pulses between which the neutron lifetime in the formation is measured (f) are separated by from each other at time intervals equal to the product of 1g by the corresponding number, for example, 12-1ZTG. The neutron density is measured during three time intervals between neutron pulses and is estimated from individual flashes of Ti-radiation, the arrival of 1 Zimis per unit time. -radiation is detected by the near detector 6. The first count rate (N), corresponding to the first count of the neutron flux density, is determined during the interval (X) equal to the neutron lifetime & . This first count begins immediately after the end of the first neutron pulse. The second (I) time interval, during which the second count rate (Nj) is calculated, starts immediately after the first interval and lasts a time period of 2t, twice the lifetime of the neutrons in the reservoir under study. In the case of the use of indicators, the background radiation is measured during the third time interval (III). The counting rate at this time interval is recorded approximately for a time of 31 / equal to three neutron lifetimes in the formation. The counting in this case begins after a time equal to BTG, after the end of the preceding neutron pulse. On the graphs 4mg. 3 shows a sequence of samples. The counting rate (Ml,) of the background radiation is subtracted from the first counting rate (N) and the second speed, the count (N,) in order to get the true counting rates N (net) and N2. (Net) for the first and second time intervals. without a background composition. These speeds characterize the density of neutron fluxes. Then the ratio N, j (net) 7Ng, (net) is obtained. The durations of the first and second detection intervals are selected in a 1: 2 ratio until the ratio of counting rates N (net) / N (net) is 2, i.e. Sudet state reached equilibrium. In this case, the measured lifetime of neutrons in the reservoir T approaches the duration (t) of the first detection interval. Deviations from this equilibrium condition lead to the triggering of a temporary block, with the help of which the width of the first transmission interval is adjusted, so that the balance is reached in the system. The signal corresponding to tj comes from the time block to the dividing unit 18 and then to register the device 19. The time (fp) unit 12 works in a similar way, producing separate accounts F., F, Rl. The counting sequence of this block is set in accordance with the measured time tp. The order of the tp-block, as well as the order of the T-block, is determined by the arrival of a synchronization pulse corresponding to the end of the preceding neutron pulse. The value of Cp from block J2 is fed to block 18 of the division and, if necessary, a recording device 19 In the absence of disturbing factors mainly associated with the scattering of neutrons and, moreover, due to the inhomogeneity of the reservoir, etc., the values of tT and T / p should be the same and equal to or 810 equal to the true value of the lifetime t. From this it follows that if the ratio t, j / tp is equal to unity, then the measurements were carried out correctly and the measured values of the thermal neutron lifetime in the reservoir under study correspond exactly to the true values. On the other hand, if the C / tp ratio differs from unity, then location in addition to significant neutron scattering and other effects that affect the accuracy of the determination. Under normal conditions, logging in a well tp should be caused by the effect of neutron scattering. Thus, ot Homemie-tj / fp can be close to unity. If the ratio t / t ... is significantly less than unity, i.e. equal, for example, 0.80, 9, then this means that the measured magnitude depends on side perturbing effects. If K is recorded,, then this parameter needs to be corrected, and hence 2 tod. This can be done using tables or graphs that take into account the effect of neutron scatter on the ratios t from the true values. FIG. 2 shows a simplified electron apparatus for measuring a neutron characteristic. A measurement information processing unit 23 descending into the earth includes a time unit (counter) 24, which is connected to the neutron source 25 and the near detector 26 via conductors 27, 28 and connected to the specifying unit 29, through which signals are sent to the surface via wires 30 and 3. The operation of the temporary block (t,) 24 is similar to the principle of operation of the same block shown in (1. 1. The output time signal is fed through wires 32 to the recording device 33. for recording. Operating signals from the far detector 34 are fed through a conductor 35 to the selector circuit 36, which is controlled by signals coming from conductors 37-39 of time block 24. Trigger signals are sent to selector block 36 from a far detector 34. These signals control the power and the onset of three time intervals, n84 during which between neutron pulses, the value of t) j is measured. These time intervals are also defined, as are the T-MI intervals, which are mentioned above. The operating signals on the time CG block come from the near detector 26. Consequently, the neutrons in the near and far detectors are counted simultaneously, and the time intervals during which the count is made coincide in time and. have the same duration. Signals corresponding to the density of neutrons and arriving at the selector unit 36 during the detail intervals are transmitted to the ground equipment via conductors 40-42, where they are processed in counting units 43. In blocks 43, the number of all ijjj radiation per unit time is counted during the first and second detection intervals. During the third period, the count rate of the " boHOBorcf-radiation, which is subtracted from the first two counts, is recorded in these blocks. The true count rates F (net) and Fe (net) from the first and second intervals, respectively, are compared in analog block 44, which produces an output equal to F (net) / 2F2 (net). . In most cases, this ratio is related to linear dependence with the ratio {c / t / |:, where Tr is the neutron lifetime constant corresponding to the rate of decrease in the thermal neutron flux measured at the far detector 34. This ratio thus determines the degree of correspondence between ttyj and trace is 14%, the accuracy of the recorded quantity. , which is used to determine the non-intact neutron lifetime tjj in the reservoir under study. From the graph of FIG. 3, it follows that the ratio F (net) / 2Fg (net) closely approximates the ratio / tp. When determining the values in block 24, it is assumed that when N (net) / Nft (net) 2 the duration (T) of the first detection interval is equal to the value of & corresponding to the velocity of the weakened neutron flux detected by the near detector. The ratio is not exactly equal to the unit N-12 while the ratio) is 7 2N (net) 1. The exact ratio of T (cl) T (t) to N (net) / 2NQ, {net) is shown by curve A in FIG. 3. Line B has a slope at an angle of 45, which corresponds to the equality of the two ratios. It was established experimentally that under normal conditions in a well, the ratio N (net) / 2N2 (net) is 0.8-1.0. Comparison of curves A and B in this range (Fig. 3) shows that this relation and the ratio T / T in the specified range (0.8-1.9) have a strictly linear dependence, triggering the signal from the time i j - block 24, arrival of the neutron source 25, in addition, is supplied to the surface via conductor 31. When the switch 45 is closed, this signal triggers the scaling blocks that transmit the total pulses I ;, (net) and Fn (net) to the buffer register5 and after the corresponding delay created by the delay line, there is a reset with ETA. On. digital to analog converter outputs form continuous voltages proportional to Fj | (net) and F2 (net). The measured signals are recorded by block 33 as a function of the depth of descent of the depth gauge. However, taking into account the strict linear dependence of the F on the wheat and IJ / tp, the ratio of the pulse counting rates is determined with the change of scale that is achieved by entering the appropriate proportionality coefficient through potentiometer 46. This allows you to increase the depth, which measures the ratio Cj, / tp. Since t and v. V.,. - are connected, then the curve Oc / tp can be replaced by the curve p. Corrections should be introduced when the ratio / tp is less than tolerated values, i.e. 0.8-0.9. In turn, reliable correction of T values is ensured by dividing 1) by the ratio tr / 1Gy, which is statistically averaged before ETU4. The averaging operation is shown in FIG. 4, where the V / tp output signal from the plasma block 23 is supplied to the registered device 33 and to the striker 47. The signal from block 23 is strewn into the registering device 33 (Fig. 4) and, together with the signal representing the signal, the average value fcy / tp is fed to the input of block 48. The division by the ratio T / tp gives the apparent value of t corresponding to the rate of decrease in the density of the neutron flux measured on the far detector 34. In FIG. 5 shows a block for automatically selecting recorded values of T or tp. This block includes an analog block (dividing circuit 49 at the input of which signals are received from center 23 and signals that represent 1p averaged value tjy | / fp, which are fed from averaging unit 50. At the output of dividing circuit 49, 49 ptrc signalTp. Signal proportional to the averaged value Сс / С |:, from block 50 is fed to discriminator 51 and to recording device 33. At discriminator 51, the measured value of tTj 1% is compared with the ehalon value. If the ratio N / F is greater than the reference value, then a trigger signal is sent to the strobe or selector unit 52, which ensures that the notfj signal passes to the recording device 33. If 1),) / tp is less than the I reference value, the discriminator sends triggering signal on tp-selector circuit 53 so that the signal on tp passes to recording device 33. The invention will improve the accuracy of measurements of the intrinsic neutron characteristic of the earth formation while simplifying the device. Claim 1. A device for measuring the earth’s intrinsic neutron characteristic, comprising a pulsed neutron radiation source, hermetically sealed in a housing, first and second radiation detectors located at different distances from the neutron source, first and second signal processing units, each of which is connected to one of the radiation detectors, a signal ratio unit, a switch, a recorder, and one of the processing units consists of a circuit, having a blue control circuit In order to increase the accuracy of measurements, a selector associated with a synchronization control circuit and an analog unit are introduced into the second processing unit, the output of the selector being connected to the input of the analog block, the output of which is connected to the recorder input. 2. The device according to claim 1, characterized in that the analog unit is implemented as a divider. Sources of information, P1 and those taken into account in the examination I. US Patent No. 3435216, cl. 250831, publ. 1969.
    [2]
    2. US patent No. 3532884 ,. cl. G 01 V 3/00, publ. 1970 (shrotiotype).
    ... "
    847948
    ""
    lAief
    7.3G .2
    1.1
    to
     2yr
    O.S
    willow
    01 0.6.
    L .. GYG
    at
    L / V, / g / V 1.0, .985
    类似技术:
    公开号 | 公开日 | 专利标题
    SU847948A3|1981-07-15|Device for measuring proper neutron characteristics of earth stratum
    US4645926A|1987-02-24|Method for induced gamma ray logging
    US4122339A|1978-10-24|Earth formation pulsed neutron porosity logging system utilizing epithermal neutron and inelastic scattering gamma ray detectors
    US2991364A|1961-07-04|Well logging
    US4409481A|1983-10-11|Method for simultaneous measurement of thermal neutron decay components
    US5349184A|1994-09-20|Method and apparatus for reducing matrix density effects on porosity measurements during epithermal neutron porosity well logging
    CA1185380A|1985-04-09|Computer-based system for acquisition of nuclear well logging data
    US4053767A|1977-10-11|Method and apparatus for stabilizing signals in radioactive well logging tools
    US3691378A|1972-09-12|Simultaneous pulsed neutron well logging
    CA1157967A|1983-11-29|Methods and apparatus for nuclear well logging
    US4122340A|1978-10-24|Pulsed neutron porosity logging system
    US4656354A|1987-04-07|Method for induced gamma ray logging
    US4239965A|1980-12-16|Method and apparatus for neutron induced gamma ray logging for direct porosity identification
    EP0387449B1|1994-05-25|Pulsed neutron porosity logging
    US3842265A|1974-10-15|Pulsed neutron well logging techniques with background radiation removal
    US3767921A|1973-10-23|Well logging system with linearity control
    US4002903A|1977-01-11|Simultaneous thermal neutron decay time and shale compensated chlorine log system
    US4430567A|1984-02-07|Method and apparatus for neutron induced gamma ray logging for direct porosity identification
    US3868505A|1975-02-25|Method and apparatus for investigating the quality of well logging data
    US3662173A|1972-05-09|Well logging method for determining the presence of aluminum and magnesium
    US3843887A|1974-10-22|Self calibrating isotopic precipitation measurement gage
    US4157469A|1979-06-05|Pulsed neutron well logging apparatus having means for determining background radiation
    US3487211A|1969-12-30|Method and apparatus for radioactivity well logging utilizing the decline of the epithermal neutron population
    US4168428A|1979-09-18|Sync transmission method and apparatus for high frequency pulsed neutron spectral analysis systems
    US4137450A|1979-01-30|Dual detector pulsed neutron logging for providing indication of formation porosity
    同族专利:
    公开号 | 公开日
    US3890501A|1975-06-17|
    FR2228226B1|1976-10-15|
    AU6800174A|1975-10-23|
    AR208665A1|1977-02-28|
    MX3204E|1980-07-04|
    NO142370C|1980-08-13|
    FR2228226A1|1974-11-29|
    OA04702A|1980-08-31|
    NO741470L|1974-11-04|
    BR7403533D0|1974-12-03|
    NO142370B|1980-04-28|
    GB1470568A|1977-04-14|
    EG13442A|1983-03-31|
    IT1010285B|1977-01-10|
    DE2420776A1|1974-12-05|
    DE2420776C2|1984-02-23|
    CA1019470A|1977-10-18|
    引用文献:
    公开号 | 申请日 | 公开日 | 申请人 | 专利标题
    US3061725A|1958-03-03|1962-10-30|California Research Corp|Comparison logging of geologic formation constituents|
    US3373280A|1963-12-18|1968-03-12|Mobil Oil Corp|Pulsed radioactive well logging method for measurement of porosity and salinity|
    US3483376A|1966-08-03|1969-12-09|Schlumberger Technology Corp|Two neutron detector earth formation porosity logging technique|
    US3566116A|1966-11-08|1971-02-23|Schlumberger Technology Corp|Method and apparatus for measuring neutron characteristics of a material surrounding a well bore|
    US3509342A|1966-12-08|1970-04-28|Schlumberger Technology Corp|Two detector pulsed neutron logging tool|
    US3546512A|1967-02-13|1970-12-08|Schlumberger Technology Corp|Neutron generator including an ion source with a massive ferromagnetic probe electrode and a permanent magnet-electrode|
    US3609366A|1968-11-01|1971-09-28|Schlumberger Technology Corp|Systems for neutron decay time well logging|
    US3662179A|1969-04-25|1972-05-09|Schlumberger Technology Corp|Pulse neutron logging tool control and transmission system|US4031367A|1975-03-31|1977-06-21|Schlumberger Technology Corporation|Methods and apparatus for pulse height analyzer offset control|
    US4267447A|1978-10-26|1981-05-12|Schlumberger Technology Corp.|Methods and apparatus for measuring thermal neutron decay characteristics of earth formations|
    US4224516A|1978-10-26|1980-09-23|Schlumberger Technology Corporation|Methods and apparatus for measuring thermal neutron decay characteristics of earth formations|
    IE49620B1|1978-10-26|1985-11-13|Schlumberger Ltd|Method and apparatus for measuring thermal neutron characteristics|
    US4292518A|1978-10-26|1981-09-29|Schlumberger Technology Corp.|Methods and apparatus for measuring thermal neutron decay characteristics of earth formations|
    US4445033A|1981-09-14|1984-04-24|Schlumberger Technology Corporation|Methods and apparatus for environmental correction of thermal neutron logs|
    US4712007A|1985-04-01|1987-12-08|S.I.E., Inc.|Pulsed neutron logging method using cumulative count curves|
    US4709234A|1985-05-06|1987-11-24|Halliburton Company|Power-conserving self-contained downhole gauge system|
    US4665398A|1985-05-06|1987-05-12|Halliburton Company|Method of sampling and recording information pertaining to a physical condition detected in a well bore|
    US4866607A|1985-05-06|1989-09-12|Halliburton Company|Self-contained downhole gauge system|
    US4663628A|1985-05-06|1987-05-05|Halliburton Company|Method of sampling environmental conditions with a self-contained downhole gauge system|
    US4883956A|1985-12-23|1989-11-28|Schlumberger Technology Corporation|Methods and apparatus for gamma-ray spectroscopy and like measurements|
    US4926044A|1986-01-31|1990-05-15|Schlumberger Technology Corporation|Thermal decay time logging method and apparatus|
    US4947040A|1989-07-14|1990-08-07|Schlumberger Technology Corporation|Thermal decay time logging method and tool|
    US5105080A|1991-04-02|1992-04-14|Schlumberger Technology Corporation|Method and apparatus for determining the respective contributions of borehole and earth formation in gamma ray spectroscopy|
    US7088097B2|2004-12-31|2006-08-08|Kjt Enterprises, Inc.|Method for fitting a sum of exponentials to experimental data by linearization using a numerical integration approximation, and its application to well log data|
    US9869791B2|2015-06-17|2018-01-16|Baker Hughes, A Ge Company, Llc|Measurement of downhole radiation|
    法律状态:
    优先权:
    申请号 | 申请日 | 专利标题
    US356150A|US3890501A|1973-05-01|1973-05-01|Neutron logging reliability techniques and apparatus|
    [返回顶部]