CN107657119B - Measurement method for improving gamma energy spectrum data quality - Google Patents
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Abstract
The invention discloses a data processing method for improving the gamma energy spectrum quality in a nuclear logging instrument by using an inversion algorithm, which can effectively reduce the counting of a Compton platform and furthest reduce the energy of gamma rays at the position where the gamma rays are incident to a detector. The data processing flow of the method is as follows: (1) and establishing a response relation matrix of the nuclear logging instrument by adopting a Monte Carlo simulation method. (2) The gamma energy spectrum data measured by a logging instrument containing a gamma detector is stored in a matrix form, the energy spectrum data of each sampling point is one column in the matrix, and different sampling points are in different columns. (3) Preprocessing the energy spectrum of each sampling point, such as energy correction, dead time correction, abnormal point elimination and the like, and ensuring that the energy spectrum quality meets the subsequent processing requirement; (4) and (3) performing inversion calculation (5) on the energy spectrum data of each sampling point by using the detector response matrix in the step (1) to obtain an inverted gamma energy spectrum, and performing corresponding subsequent spectrum processing on the energy spectrum.
Description
The technical field is as follows: the invention belongs to the field of petroleum logging, and relates to a data processing method for improving the gamma energy spectrum quality in a nuclear logging instrument based on a data inversion method, so that the sensitivity and the measurement precision of logging curve variables are improved.
Background art:
in the field of petroleum nuclear logging, whether natural gamma-ray logging, density logging, lithology logging or logging instruments using neutron sources, gamma detectors are used in these logging instruments to measure gamma energy and counts. Some of the logging instruments have a high requirement on energy resolution of the gamma detector, for example, in a full-spectrum logging in a neutron-gamma logging instrument, the content or ratio of different elements in the formation needs to be calculated and analyzed through the measured gamma energy spectrum, and the accuracy of the measurement result is directly affected by the level of the energy spectrum resolution of the detector.
In a conventional nuclear logging tool, due to the generally small diameter of a borehole, the sensitive volume of a gamma detector (e.g., the crystal size of a crystal detector) in the tool is generally limited by the space inside the tool, which results in the gamma ray not being able to deposit all energy in the sensitive region, and thus results in fewer counts of the full energy peak positions in the gamma ray spectrum and more counts on a compton platform. However, the energy of the full energy peak is generally the characteristic energy of the formation elements, and how to improve the counting of the full energy peak has important significance for improving the measurement accuracy of the instrument.
The invention content is as follows:
the purpose of the invention is as follows: the invention discloses a data processing method for improving the gamma energy spectrum quality in a nuclear logging instrument by using an inversion algorithm, which can effectively reduce the counting of a Compton platform and furthest reduce the energy of gamma rays at the position where the gamma rays are incident to a detector.
The technical scheme is as follows:
a measurement method for improving the quality of gamma energy spectrum data is characterized in that: the method comprises the following steps:
(1) establishing a geometric and physical model of a gamma detector in a corresponding logging instrument by utilizing a particle transport Monte Carlo simulation tool;
(2) simulating a response relation matrix between detector input energy and output energy spectrum: the energy spectrum measured by the detector due to gamma energy deposition is considered as the integral of the incident gamma ray energy and the response function, as follows:
wherein:
d (e) is the spectrum measured by the detector, i.e. the output spectrum;
I(E0) Is the energy spectrum of the gamma ray before incidence on the detector position;
R(E,E0) Is the response equation of the detector;
the expression in discrete matrix is as follows:
wherein:
Rijis the probability that the incident ray with energy in the ith energy track is in the jth energy track when measured by the detector;
Dnis the count on the nth energy track of the energy spectrum measured by the detector;
Inis the nth energy of the spectrum incident on the detector surfaceCount on track;
(3) storing gamma energy spectrum data of each sampling point, namely a time point or a depth point of the logging instrument into a matrix form;
(4) preprocessing the energy spectrum of each sampling point of the logging instrument in the step (3);
(5) and (3) combining the response relation matrix in the step (2) to perform data inversion on the sampling points in the step (4), wherein an iterative inversion formula is as follows:
wherein:
(6) And iterating for a plurality of times until a set condition is met, and finally obtaining the gamma energy spectrum after inversion.
The measurement method for improving the data quality of the gamma energy spectrum preferably comprises the following steps: the response equation matrix R in the step (2)ijThe specific obtaining method is to simulate the response value of the detector after each single-energy gamma incident ray of the detector enters the crystal by adopting the Monte Carlo technology; for example simulation I1Not zero, the rest IiAll are zero, and the response result D of the detector, namely the response coefficient R is obtainedi1(ii) a And the whole response relation matrix can be obtained by analogy.
The measurement method for improving the data quality of the gamma energy spectrum preferably comprises the following steps: preprocessing the energy spectrum of each sampling point, wherein the preprocessing comprises energy correction, dead time correction, abnormal point elimination and the like, and the energy spectrum quality is ensured to meet the subsequent processing requirement; the energy is modified such that the measured energy reflects the true energy.
Description of the drawings:
FIG. 1 is a process flow of improving the gamma spectrum quality by using an inversion calculation method according to the present invention;
FIG. 2 is a comparison of the measured spectrum and the spectrum of the method;
FIG. 3 is a comparison of energy spectrum integration curves;
the advantages and effects are as follows: the method can effectively reduce the count of the Compton platform and reduce the energy of gamma rays at the position where the gamma rays are incident to the detector to the maximum extent.
The specific implementation mode is as follows:
the invention carelessly omits a data processing method for improving the gamma energy spectrum quality in a nuclear logging instrument by using an inversion algorithm, the method can effectively reduce the counting of a Compton platform, and the energy of gamma rays at the position of an incident detector is reduced to the maximum extent. The data processing flow of the method is as follows:
as shown in fig. 1:
(1) and establishing a mathematical geometry and physical model of the nuclear logging instrument by adopting a Monte Carlo simulation method, and simulating to obtain a response relation matrix between incident energy and deposition energy of the detector.
(2) The gamma energy spectrum data measured by a logging instrument with a gamma detector is stored in a matrix form, the energy spectrum data of each sampling point (time point or sampling point) is one column in the matrix, and different sampling points are in different columns.
(3) Preprocessing the energy spectrum of each sampling point, such as energy correction, dead time correction, abnormal point elimination and the like, and ensuring that the energy spectrum quality meets the subsequent processing requirement;
(4) performing inverse calculation on the energy spectrum data of each sampling point by using the detector response matrix in the step (1)
(5) And obtaining the inverted gamma energy spectrum, and performing corresponding subsequent spectrum processing on the energy spectrum, such as extracting the counting ratio of each energy window and the like.
The specific implementation method of the method comprises the following steps:
(1) and establishing a geometric and physical model of the gamma detector in the corresponding logging instrument by utilizing a particle transport Monte Carlo simulation tool, such as GEANT4, MCNP and the like.
(2) And simulating a response relation matrix between the input energy and the output energy spectrum of the detector. The energy spectrum measured by the detector due to gamma energy deposition can be regarded as the integral of the incident gamma ray energy and the response function, as follows:
wherein:
d (E) is the spectrum measured by the detector, i.e. the output spectrum
I(E0) Is the spectrum of the gamma ray before it is incident on the detector location
R(E,E0) Is the response equation of the detector.
The expression in discrete matrix is as follows:
wherein:
Rijis the probability that the incident ray with energy in the ith energy track is in the jth energy track when measured by the detector.
DnIs the count on the nth energy trace of the spectrum measured by the detector.
InIs the count on the nth energy trace of the spectrum incident on the detector surface.
The most important thing in this process is to obtain a matrix R of response equations between the incident energy and the measured energyijThe specific method is to adopt a Monte Carlo technology to simulate the response value of the detector after each single-energy gamma incident ray of the detector enters the crystal. For example simulation I1Not zero, the rest IiAll are zero, and the response result D of the detector, namely the response coefficient R is obtainedi1. And the whole response relation matrix can be obtained by analogy.
(2) The gamma energy spectrum data of each sampling point (time point or depth point) of the logging instrument is stored in a matrix form, for example, the energy spectrum of a certain measuring point is recorded as: E. the energy spectrum data of each sampling point (time point or sampling point) is one column in the matrix.
(3) Preprocessing the energy spectrum of each sampling point, such as energy correction, dead time correction, abnormal point elimination and the like, and ensuring that the energy spectrum quality meets the subsequent processing requirement; in particular energy correction, so that the measured energy reflects the real energy.
(4) And (3) inverting the data of each sampling point by combining the response matrix of the detector, wherein an iterative inversion formula is as follows:
wherein:
(5) And iterating for a plurality of times until a set condition is met, and finally obtaining the gamma energy spectrum after inversion. At this time, the obtained new energy spectrum may be subjected to corresponding subsequent spectrum processing, such as extracting the ratio of counts in different energy windows, and the like.
As shown in fig. 2 and 3:
in fig. 2, the green line is the measured gamma spectrum, and the red line represents the new spectrum obtained by the inventive careless method;
in fig. 3, a comparison of energy spectrum integration curves. Blue represents gamma rays before entering the gamma detector, green is an unprocessed gamma energy spectrum integral curve, and red is a curve processed by the method. It can be seen that after processing by the method, the integral curve is very close to the integral curve of the gamma energy spectrum before incidence on the detector.
Claims (3)
1. A measurement method for improving the quality of gamma energy spectrum data is characterized in that: the method comprises the following steps:
(1) establishing a geometric and physical model of a gamma detector in a corresponding logging instrument by utilizing a particle transport Monte Carlo simulation tool;
(2) simulating a response relation matrix between detector input energy and output energy spectrum: the energy spectrum measured by the detector due to gamma energy deposition is considered as the integral of the incident gamma ray energy and the response function, as follows:
wherein:
d (e) is the spectrum measured by the detector, i.e. the output spectrum;
I(E0) Is the energy spectrum of the gamma ray before incidence on the detector position;
R(E,E0) Is the response equation of the detector;
the expression in discrete matrix is as follows:
wherein:
Rijis the probability that the incident ray with energy in the ith energy track is in the jth energy track when measured by the detector;
Dnis the count on the nth energy track of the energy spectrum measured by the detector;
Inis the count on the nth energy trace of the spectrum incident on the detector surface;
(3) storing gamma energy spectrum data of each sampling point, namely a time point or a depth point of the logging instrument into a matrix form; the energy spectrum data of each sampling point is a column in the matrix;
(4) preprocessing the energy spectrum of each sampling point of the logging instrument in the step (3);
(5) and (3) combining the response relation matrix in the step (2) to perform data inversion on the sampling points in the step (4), wherein an iterative inversion formula is as follows:
wherein:
(6) and iterating for a plurality of times until a set condition is met, and finally obtaining the gamma energy spectrum after inversion.
2. The method of claim 1, wherein the method comprises: the response equation matrix R in the step (2)ijThe specific obtaining method is to simulate the response value of the detector after each single-energy gamma incident ray of the detector enters the crystal by adopting the Monte Carlo technology; when simulating I1Not zero, the rest IiAll are zero, and the response result D of the detector, namely the response coefficient R is obtainedi1(ii) a And the whole response relation matrix can be obtained by analogy.
3. The method of claim 1, wherein the method comprises: preprocessing the energy spectrum of each sampling point, wherein the preprocessing comprises energy correction, dead time correction and abnormal point elimination, and the energy spectrum quality is ensured to meet the subsequent processing requirement; the energy is modified such that the measured energy reflects the true energy.
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| CN110068856B (en) * | 2019-04-16 | 2021-04-13 | 东莞中子科学中心 | A calculation method of neutron energy spectrum based on C++ language and ROOT data analysis |
| CN111119845B (en) * | 2019-12-31 | 2023-10-27 | 北京环鼎科技有限责任公司 | 63 gamma-ray spectroscopy three-probe logging instrument and logging method thereof |
| CN111553110B (en) * | 2020-04-22 | 2023-03-24 | 西北核技术研究院 | Monte Carlo simulation-based nuclear electromagnetic pulse current source term calculation method |
| CN114371496B (en) * | 2021-12-15 | 2025-01-21 | 中国科学院合肥物质科学研究院 | A method for measuring tritium content in solid materials |
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