232 results about "Gamma ray" patented technology

A detector system for molecular imaging of a radionuclide comprises a 3D semiconductor detector comprising a plurality of sensor stacks of sensors made of a semiconductor material having an average atomic number Z below 40. A read-out circuitry connected to the pixels is configured to output, for each interaction induced by an incident gamma ray in the detector, a signal representative of a time, a position and an energy of the interaction in the detector. The interactions in the detector belonging to a same event induced by the incident gamma ray are predicted based on the output signals and used to estimate a direction of the incident gamma ray and reconstruct an image based on the estimated directions of incident gamma rays.

The invention discloses a method for efficiently generating high-brightness gamma radiation, and belongs to the technical field of radiation. A relativistic electron beam is injected into the porous microstructure foam target material, and high-brightness gamma ray radiation is generated. According to the method, the used device is simple, only the single relativistic electron beam and the porous microstructure foam target material are needed to interact, compared with a traditional uniform-density solid material, the energy conversion efficiency in the interaction process of the electron beam and a substance can be remarkably improved, and the energy conversion efficiency can be remarkably improved through the effective constraint effect of a high-intensity magnetic field. And the problems of low energy conversion rate, low light source brightness, poor radiation directivity, complex device or difficulty in experiment implementation and the like of the existing high-energy gamma ray radiation source are solved.

The invention provides a radioactive internal pollution detection method and system based on a dynamic efficiency scale, and the method comprises the steps: carrying out the detection of the radioactive internal pollution based on a pre-obtained change table of the total detection efficiency of a detector for the radionuclide in a human body along with the time; determining the total detection efficiency of the radiation detector on the radionuclides in the human body according to the interval time and the types of the radionuclides; and obtaining the activity of the internal pollution radionuclides based on the characteristic gamma ray full-energy peak counting and the total detection efficiency of the radiation detector on the radionuclides in the human body. In-vivo metabolism behaviors of nuclides are considered, so that the internal pollution detection accuracy is greatly improved. The problems that in the prior art, equipment is large in size, high in manufacturing cost, long in measurement time consumption, complex in operation and the like are solved. The method is suitable for rapid detection and classification of mass personnel in nuclear and radiation accident emergency sites.

The invention discloses a polyamide / polyphenyl ether alloy material and a manufacturing method thereof, and is used for solving the problems that an existing polyamide / polyphenyl ether alloy material cannot meet UL94 V-0-level flame retardance, high insulativity of CTI greater than or equal to 700V and low precipitation (lt) after long-term damp-heat aging at the same time under the ultra-thin thickness of 0.6 mm; 0.1%) and a high performance retention rate (gt; 90%). The polyamide / polyphenyl ether alloy material comprises the following components in parts by mass: 55-75 parts of polyamide 66 resin; 25 to 45 parts of polyphenyl ether resin pre-irradiated by gamma rays; 10 to 20 parts of a silicone-coated diethyl aluminum phosphinate flame retardant with a core-shell structure; 5-10 parts of a maleic anhydride grafted high impact polystyrene compatilizer pre-irradiated by gamma rays; 20-30 parts of hydrolysis-resistant glass fiber of which the surface is treated by a silane coupling agent; 3-8 parts of tetrapod-like zinc oxide whiskers; 2 to 5 parts of a CTI synergist; and 1-2 parts of an anti-precipitation agent.

This application proposes methods for synthesizing aromatic compounds using ionizing radiation based on N₂O, and methods for synthesizing aromatic compounds using industrial waste gas. The method includes: placing benzene and a combined gas containing N₂O in a sealed container, and adjusting the volume of the combined gas to bring the benzene in the sealed container to its saturated vapor pressure; irradiating the sealed container with radiation to cause the benzene to react and yield the aromatic compounds, wherein the radiation includes X-rays, gamma rays, or electron beams, the energy range of which is 0.0110 MeV, and the absorbed dose rate is 0.1 Gy / min to 1000 kGy / min. This method can synthesize aromatic compounds such as phenol in one step using ionizing radiation based on N₂O without the use of a catalyst, achieving precise and high-value utilization of N₂O.

The invention relates to a real-time magnetic resonance guided head gamma beam stereotactic radiotherapy system, which comprises a magnet module, a gamma beam module, a treatment bed module and a source body driving assembly, the magnet module comprises a base, a left vertical yoke and a right vertical yoke which are arranged on two sides of the base, and a left magnetic pole and a right magnetic pole which are respectively arranged on the inner side of the left vertical yoke and the inner side of the right vertical yoke; the left magnetic pole and the right magnetic pole are arranged in parallel; a Y-axis linear guide rail is arranged on the base; the gamma beam module comprises a shielding body assembly, a source body assembly and a collimation body assembly, wherein the source body assembly and the collimation body assembly are arranged in the shielding body assembly and are coaxially nested. The shielding body assembly is fixedly connected with the left vertical yoke and the right vertical yoke; the treatment bed module is arranged on the Y-axis linear guide rail, and the source body driving assembly is connected with the source body assembly. According to the invention, clear imaging of cranial soft tissue in a high field intensity environment can be realized, gamma rays are guided to carry out real-time image-guided stereotactic radiotherapy, and the radiotherapy precision is improved.

A boron dose measurement system, method and apparatus. The system is provided with a first detection apparatus (10), a second detection apparatus (20) and a boron dose measurement apparatus (30), wherein the first detection apparatus (10) detects gamma rays in a target region, in order to obtain first boron measurement information, the first boron measurement information comprising energy spectrum information of the gamma rays; the second detection apparatus (20) detects the gamma rays in the target region, in order to obtain second boron measurement information, the second boron measurement information comprising position information of the gamma rays; the second detection apparatus (20) and the first detection apparatus (10) synchronously perform measurement; and the boron dose measurement apparatus (30) can determine a boron dose distribution in the target region on the basis of the energy spectrum information and the position information of the gamma rays that are obtained by means of synchronous measurement. A boron dose distribution in a target region can be accurately obtained, and the obtained boron dose distribution can meet the requirements for online boron dose monitoring.

The present application relates to a kind of for the radiation protection detection in nuclear magnetic machine room, including: shielding sleeve box, by diamagnetic material is made, for shielding external static magnetic field, its internal cavity shape is adapted according to the shape of the used patrol instrument;Ray detection mesh, set up on shielding sleeve box corresponding to the position of patrol instrument probe, by diamagnetic material is made, allow X or gamma ray to penetrate;Instrument data reading mesh, set up on shielding sleeve box corresponding to the position of patrol instrument display screen, by diamagnetic material is made, allow detection personnel to read data directly visually;The import and export of instrument that can be closed, be set on shielding sleeve box, and be equipped with the sealing cover made of diamagnetic material, for the input and output of patrol instrument, the sealing cover is in closed state when detecting.The present application solves the phenomenon that the radiation diagnosis and treatment machine room adjacent place is the radiation protection detection difficult to implement for nuclear magnetic resonance machine room.

The invention provides an online diagnosis and repair method for a uranium mine gamma ray monitoring device, and the method comprises the steps: determining the respective counting rate correction values of a plurality of detectors based on the current working temperature of the uranium mine gamma ray monitoring device, a preset temperature compensation model, and the counting rate detection values of the plurality of detectors; based on the respective counting rate correction values of the plurality of detectors, the detection efficiency of each detector is determined, and the detection efficiency comprises static detection efficiency and dynamic detection efficiency; and if the detection efficiency of any first detector in the plurality of detectors is deviated from the detection efficiency of a specified second detector in the plurality of detectors, circuit parameters of the first detector are adjusted based on the deviation, so that the detection efficiency of the first detector after the circuit parameters are adjusted is consistent with the detection efficiency of the second detector. According to the technical scheme, the measurement precision and the detection efficiency of the uranium ore gamma ray monitoring device in continuous operation are improved, and the uranium ore sorting energy efficiency is improved.

This invention relates to the field of nuclear radiation detection technology, and more particularly to an energy spectrum processing method for a quasi-hemispherical CdZnTe detector. The method includes: acquiring the raw signal collected by the quasi-hemispherical CdZnTe detector; normalizing the amplitude of the raw signal from the baseline to the highest point during the rise phase; dynamically selecting multiple energy thresholds; performing rise time discrimination on the normalized signal within each energy threshold; filtering out signals with rise times greater than RTflag and determining the rise time range corresponding to that energy threshold; constructing an intermediate energy spectrum corresponding to each energy threshold based on the signals with rise times greater than RTflag and the rise time range; and post-processing the intermediate energy spectrum to obtain the target energy spectrum corresponding to each energy threshold. This invention combines energy threshold discrimination, rise time discrimination, and energy spectrum post-processing algorithms to stably improve the energy resolution of the quasi-hemispherical CdZnTe detector for 662 keV gamma rays from the conventional 2%~3% to less than 1%.

The invention belongs to the technical field of diluted magnetic semiconductor films, and particularly discloses a method for enhancing the magnetism of a Y-doped HfO2 diluted magnetic semiconductor film through gamma ray induction, and the method comprises the following steps: S1, placing a Y-doped HfO2 target material in a radio frequency device, fixing a 111-oriented YSZ substrate at the central position of a dial plate of the radio frequency device, and enabling the target material to correspond to the substrate; s2, turning on a radio frequency power supply, and officially sputtering after glow is stable to obtain a thin film; s3, annealing the film in a muffle furnace; and S4, placing the annealed film sample in a gamma ray device with 60Co as an irradiation source for irradiation to realize total ion implantation dose treatment. According to the method for enhancing the magnetism of the Y-doped HfO2 diluted magnetic semiconductor thin film through gamma ray induction, the problem that the saturation magnetization intensity of an existing diluted magnetic semiconductor thin film is not high is solved, and the magnetism of the Y-doped HfO2 epitaxial thin film is enhanced, regulated and controlled through gamma ray micro dose.

The present application relates to the technical field of oil drilling downhole testing instrument, and particularly relates to a small-size geological parameter measuring short circuit. The small-size geological parameter measuring short circuit comprises a position gamma skeleton and a gamma sensor. The device is provided with a plurality of circular-arc-shaped slots as installation bins on the outer wall of the skeleton for installing the gamma sensor, the position gamma sensor, the main control board, the power board and the magnetometer. The compact design realizes comprehensive measurement of various geological parameters and reduces the overall size. The outer wall of the skeleton is designed with a wear-resistant ring to improve the durability of the device. The shielding layer realizes partition control of the gamma rays to improve the measurement accuracy. The outer wall of the main control board, the power board and the magnetometer is covered with high-temperature-resistant soft rubber to ensure stable performance in extreme environments. The small-size geological parameter measuring short circuit can be hung near the drill bit to realize real-time edge detection, help identify and locate sandstone layers, improve the sandstone drilling rate and discover the deviation of the drilling trajectory in time.

The invention relates to a method for radiation detection chip angle response compensation. The method comprises the following steps: step 1, testing the counting rate of deposition of each channel of array SiPM when gamma rays have different incident angles; 2, according to a standard dose rate value and the counting rate of each channel of the array type SiPM at different incident angles obtained in the step 1, constructing a linear equation set; 3, solving the system of linear equations in the step 2 to obtain an angle response correction matrix; and 4, correcting the angle response of the chip according to the angle response correction matrix in the step 3. According to the invention, the angle response compensation of the thin-layer scintillator radiation detection chip on the directional dose rate of different incident angles is realized, and the problem of measurement deviation of the radiation detection chip caused by the change of the incident angle of the radiation source is solved.

A method of deploying a pulsed neutron logging tool. The method may comprise detecting natural gamma rays from the subterranean formation via one or more detectors of the pulsed neutron logging tool, broadcasting neutrons into the subterranean formation, and detecting neutron-induced gamma rays and natural gamma rays from the subterranean formation. The method may further comprise creating an inelastic spectrum, a capture spectrum, or a capture time decay from the natural gamma rays or the neutron-induced gamma rays, forming an inelastic yields, a capture elemental yields, or a formation sigma form the inelastic spectrum, the capture spectrum, or the capture time decay, creating a closure model from the inelastic yields and / or capture elemental yields and / or a formation sigma, and identifying a porosity, a mineral weight fraction, or a quality figure of merit from the closure model that quantifies geologic hydrogen reservoir quality.

The invention discloses a liquid-phase deuterium-doped anti-radiation optical fiber, a preparation method and application, and belongs to the technical field of manufacturing of anti-radiation optical fibers. According to the method, deuterium is stably doped into a fiber core in the form of OD groups in the preparation stage of the optical fiber preform through an improved chemical vapor deposition combined solution doping technology, so that the problems that gas is easy to leak and the radiation resistance is attenuated along with time in a traditional gas loading technology are solved. The preparation process comprises the steps of pretreatment of the deposition tube, preparation of the barrier layer and the porous loose layer, solution soaking OD group doping, sintering collapse and wire drawing treatment. An OD group can be detected in the prepared optical fiber, the radiation resistance of the optical fiber is remarkably improved, after the optical fiber is irradiated by gamma rays with the total dose of 200Gy (Si), the radiation-induced attenuation is remarkably lower than that of a common optical fiber without the OD group, and a material basis is provided for long-term reliable application of the optical fiber in radiation environments such as space exploration and nuclear facilities.

The application discloses a method and device for improving the saturation drain-source current of an encapsulated enhanced gallium nitride power device, characterized by irradiating the encapsulated enhanced P-type cap layer gallium nitride power device with gamma rays, controlling the energy of the gamma rays to be 1.25 MeV, the dose rate to be 10-50 rad(Si) / s, and the total dose to be 600-800 krad(Si), so that positive charge defects are introduced into the P-type cap layer of the enhanced gallium nitride power device, the effective doping of the channel is improved, and the saturation drain-source current of the encapsulated enhanced gallium nitride power device is increased; the method has the advantages of solving the current situation that the parameters of the enhanced P-type cap layer gallium nitride power device cannot be optimized after encapsulation, being mature and stable in technology, causing little environmental pollution, not needing to add other chemical substances during the irradiation process, and being low in cost.

The present application relates to the technical field of agricultural equipment, and discloses an alfalfa planting and topdressing device and a topdressing method, which comprise: a lightweight mobile frame, a connecting head connected with a power end, a front wheel and an infrared laser radar arranged at the front end, and an adjustable rear wheel group arranged at the rear end; a multi-modal detection unit integrated with the front wheel, a detection surface of the multi-modal detection unit and a scanning direction of the infrared laser radar form a spatial orthogonal layout, and the multi-modal detection unit comprises: a rolling trigger type gamma ray sensor which periodically emits rays while rotating with the front wheel; through the cooperative work of the multi-modal detection unit, the present device realizes comprehensive perception of soil deep nutrients, ion concentration, surface moisture and plant canopy, combines the terrain scanning function of the infrared laser radar, and dynamically generates a fertilizer formula and adjusts fertilization parameters, so that the precision and adaptability of fertilization are significantly improved, and the limitations of traditional single detection means are avoided.

The invention relates to the technical field of radiation measurement, in particular to a high-radioactivity volatile liquid on-line measuring device and method.The measuring device comprises an overflow pool, a lead shielding body and a detector, a detection channel is formed in the axis area of the lead shielding body in the vertical direction in a penetrating mode, and an orifice in the bottom of the detection channel is sealed through a window plate; a detector is coaxially arranged in the detection channel, and a light-sensitive surface of the detector directly faces the window plate; the lower end of the lead shielding body is embedded and fixed at the top opening of the overflow pool, so that the top of the overflow pool and the bottom of the lead shielding body define an annular airflow channel. The detector is arranged in the detection channel in the lead shielding body, and the dynamic air curtain isolation layer is constructed between the bottom of the lead shielding body and the liquid level of the overflow pool, so that the upward diffusion of volatile radioactive substances is physically blocked while gamma ray penetration measurement is realized, the detector and a light-sensitive surface are fundamentally prevented from being polluted, the maintenance frequency is remarkably reduced, and the measurement accuracy is improved. And the long-term measurement precision and the online continuous operation capability of the system are ensured.

This invention relates to the fields of brachytherapy and radiosensitization, specifically providing a... 125 I-nano implantable particles, their preparation methods, and applications. 125 The 1-nanometer implanted particles have a core-shell structure, consisting of a particle core and particles adsorbed on the outer surface of the particle core. 125 I and the particles encapsulated in the nucleus and 125 The outer shell of the I-type photosensitizer is a covalent organic framework. This invention... 125 The core of the I-nanometer implanted particle is used to enhance the energy deposition of gamma rays and X-rays, generating more hydroxyl radicals; the shell containing a type I photosensitizer is used to absorb the energy of Auger electrons and internal conversion electrons and excite the photosensitizer to generate singlet oxygen, effectively improving the response to... 125 The efficiency of I decay energy utilization. 125 I-nano implanted particles, combined with internal radiation therapy and radiodynamic therapy, destroy tumor cell DNA and cell membranes, enhance tumor killing and induce immunogenic cell death, thereby activating anti-tumor immunity and inducing remote effects.

The invention relates to a flat plate ionization chamber capable of measuring beta, X and gamma rays and a use method thereof, one side of an ionization chamber main body is provided with an incident window film, the incident window film side is provided with a balance cover, the balance cover is provided with a vent hole, and the vent hole is arranged on a circular plane of the balance cover; the spring needle is arranged in the ionization chamber main body and is in contact connection with the incident window film; the spring needle stud is located at the rear end of the spring needle, abuts against the rear wall of the ionization chamber body and is used for abutting against the spring needle to make continuous contact with the incidence window film. And the high-voltage conductive column is connected with the spring needle, is connected with an external power supply and is used for applying voltage to the incident window film through the spring needle. The balance cover is arranged in front of the ionization chamber main body, the balance cover provides a secondary electron balance condition for the ionization chamber to measure the strong penetrating radiation, the strong penetrating radiation can be measured by the ionization chamber, on the contrary, when the balance cover is removed, the weak penetrating radiation can be measured by the ionization chamber, and the strong penetrating radiation and the weak penetrating radiation can be measured by one ionization chamber. And the effect of weak through radiation can also be measured.

The invention relates to the technical field of water treatment, and discloses a method and a device for recycling bromine triions based on irradiation coupling electronic control ion exchange and application, the method comprises the following steps: placing a bromine-containing stock solution in an electronic control ion exchange device which is a single-chamber device, irradiating the bromine-containing stock solution by using gamma rays, bromine ions in the bromine-containing stock solution are oxidized and react to form bromine triions; and then switching on a circuit and applying an oxidation potential to the working electrode to drive the bromine triions to directionally move towards the membrane and adsorb the bromine triions, and selectively recovering the bromine triions. The device comprises a single-chamber reactor, a liquid path system, a gamma-ray irradiation source for the single-chamber reactor, an electrochemical driving system, a two-electrode system with electrodes immersed in a bromine-containing stock solution, and a potential control system.

The nuclear medicine diagnostic apparatus according to an embodiment includes a frame apparatus and a console apparatus. The frame apparatus generates single event data based on annihilation gamma rays emitted from a subject. The console apparatus executes pairing processing to identify a combination of two pieces of the single event data. The pairing processing is executed on the single event data being stored in a first memory and corresponding to a first period of time. The console apparatus deletes the single event data that corresponds to a second period of time in the first period of time, and to which pairing processing has been applied. The console apparatus executes pairing processing on both the single event data corresponding to a third period of time in the first period of time and the single event data corresponding a fourth period of time following the first and third periods of time.

The invention relates to a radioisotope tracer strain clamp cavity grease injection amount detection system and method, and provides a method for preparing electric grease containing a low-energy gamma-ray isotope tracer agent, injecting the electric grease into a strain clamp cavity, sealing, scanning in a lead shielding detection cabin by using a high-resolution sodium iodine detector, and detecting the grease injection amount of the strain clamp cavity. And the grease thickness of each area is calculated according to the Lambert-Beer law, and the total grease injection amount is obtained through accumulation. According to the method, non-contact measurement is adopted, the detection sensitivity reaches 0.01 ml, the method is suitable for detecting small-size cavities and is particularly suitable for complex shapes such as deep holes and narrow slits, and the problem of low resolution in the prior art is solved; in addition, the radiation dose in the detection process is lower than 0.1 mu Sv, safety is ensured, the quality control risk is reduced, and the maintenance reliability of the power system is improved.

This invention provides a gamma-ray-based tank parameter measurement device, installed on a working tank, comprising: a radiation source, a level gauge, at least two thickness gauges, and a control host. The installation height of each thickness gauge corresponds to the installation height of one of the radiation sources, making the thickness gauge and radiation source radially symmetrical on the working tank, forming an independent through-beam measurement optical path. The control host receives the level signal and triggers the thickness gauge to perform wall thickness measurement when the material level drops below the installation height of one of the thickness gauges. This invention significantly extends equipment lifespan by having the control host trigger measurement only when the material level drops below the installation position of a certain thickness gauge, while the thickness gauge remains silent at other times. It also ensures that measurements are performed in an empty tank window free from material interference, resulting in accurate and valid data. The hysteresis range setting prevents frequent start-stop cycles caused by level fluctuations, ensuring stable and reliable system operation.

The application relates to a high-radiation shielding particle material and a preparation method thereof, and belongs to the technical field of shielding materials. The application aims to solve the problems that the existing radiation shielding materials cannot have the shielding performance of gamma rays, good flexibility and convenient construction performance and the like, and the particle material is composed of glass microspheres, a chemical nickel plating layer, an electroplated lead layer, an electroplated tungsten layer and an electroplated tantalum layer. The thickness of each layer is controlled to be 20 mu m. The method is that nickel is deposited on the surface of the glass microspheres by a chemical nickel plating method, and then an electroplated lead layer, an electroplated tungsten layer and an electroplated tantalum layer are sequentially deposited by an electroplating method. The glass microspheres are pretreated, and nickel is deposited on the surface of the glass microspheres by a chemical nickel plating method, so that other electroplated layers can be more easily deposited on the surface; the electroplated lead layer and the electroplated tungsten layer have the characteristics of good combined shielding performance of gamma rays and neutrons; and the metal tantalum layer has good gamma ray shielding performance and excellent mechanical performance.

This invention discloses a method for controlling the simultaneous fracturing of multiple clusters in a horizontal well. The steps include: Step 1: acquiring logging data from multiple vertical wells in the target reservoir; Step 2: calculating the fracturing pressure using the P-wave transit time data of the vertical wells; Step 3: establishing a graph showing the relationship between natural gamma ray and fracturing pressure; Step 4: calculating the fracturing pressure of each perforation cluster in the horizontal well; Step 5: calculating the number of perforations in each perforation cluster. This method uses logging data from vertical wells in the target reservoir to establish a graph showing the relationship between natural gamma ray and fracturing pressure, overcoming the problem of limited data for horizontal wells and the inability to determine the number of perforations in multi-cluster fracturing. Using this method, the number of perforations in each perforation cluster can be determined, avoiding problems such as incomplete fracturing or uneven fracturing, increasing the fracturing volume, and improving post-fracturing productivity.

The application discloses a wide-energy gamma ray standard surface source and a preparation method thereof, and aims at solving the technical problems that the existing radioactive sources cannot meet high-precision measurement due to short service life, uneven distribution of radioactive sources, and self-absorption, etc. The wide-energy gamma ray standard surface source comprises a radioactive source carrier, a sealed shell and a sealed cover. The radioactive source carrier is laid on the bottom of the sealed shell, and radioactive nuclides are attached to the radioactive source carrier. 226 Ra 226 The activity of Ra is not less than 5*10 4 Bq. The sealed cover is tightly pressed on the radioactive source carrier, and the gap between the sealed cover and the sealed shell is sealed by sealing glue, so that the radioactive source carrier is sealed between the sealed shell and the sealed cover.

The invention provides a radiation detection element, a radiation detector, and a method for manufacturing the radiation detection element capable of performing energy measurement of radiation with good precision. A radiation detection element includes: a compound semiconductor crystal substrate formed of zinc cadmium telluride to which indium is added as an impurity; and a metal electrode that is provided on the surface of the compound semiconductor crystal substrate. The energy resolution of the metal electrode with respect to 122 keV gamma rays emitted from 57 Co is 7% or less.

The invention relates to a gamma ray source identification and imaging instrument and a gamma ray imaging system, and belongs to the technical field of nuclear radiation detection and imaging. The gamma ray source identification and imaging instrument comprises a shell and a gamma detector module arranged in the shell, wherein the gamma detector module comprises a scattering detector and an absorption detector which are sequentially arranged along a preset direction; each of the scattering detector and the absorption detector comprises a crystal array and a photoelectric detector array; and the gamma ray source identification and imaging instrument is configured to transmit a radiation detection signal obtained by the gamma detector module to the upper computer so as to display a radiation energy spectrum and a radiation image. According to the gamma ray source identification and imaging instrument, collimation of the gamma ray direction can be achieved without a heavy mechanical collimator, the gamma ray source identification and imaging instrument has the gamma ray source nuclide identification and space positioning capacity, high-sensitivity imaging can be achieved, and the gamma ray source identification and imaging instrument has the advantages of being compact, small, exquisite and portable.

A method is described for characterizing near-wellbore lithology, mineralogy, and heterogeneity, including receiving azimuthal gamma ray data from a horizontal well; calculating a difference between an up-sector gamma ray signal and a down-sector gamma ray signal and normalizing the difference by an average gamma ray value to generate a gamma ray difference value; using the gamma ray difference value to identify heterogeneous intervals along the horizontal well to generate a heterogeneity index; and using the heterogeneity index for at least one of geomechanical analysis of wellbore stability, drilling performance analysis, fracturing decisions, and production performance diagnosis. The method is executed by a computer system.