457 results about "Gamma ray" patented technology

The invention discloses a hybrid neutron gamma detector array and a signal processing method, and relates to the technical field of nuclear physical detection.During detection, eight EJ200 scintillators arranged in an array are used for energy deposition of gamma rays and fast neutrons and generating photons, and meanwhile three EJ426 thermal neutron scintillation screens are used for capturing thermal neutrons and generating photons; the response of gamma rays, fast neutrons and thermal neutrons is realized at the same time, and the detection precision is greatly improved. Meanwhile, if the three EJ426 thermal neutron scintillation screens are alternately stacked front and back, the total reflection of the EJ200 scintillators and the semi-light-proof performance of the EJ426 thermal neutron scintillation screens are utilized to block photon propagation in the X direction and only enable photons to be propagated in the Y direction and the Z direction, and each EJ200 scintillator corresponds to a four-channel photon collection structure to perform high-efficiency collection of the photons, so that the high-efficiency collection of the photons is realized. Therefore, high-precision detection and high-efficiency photon collection are realized, and support is provided for subsequent intense radiation field monitoring or high-precision positioning.

The invention relates to the technical field of radiation therapy, in particular to a boron neutron capture therapy beam shaping device and a boron neutron capture therapy system. The beam shaping device for boron neutron capture therapy is used for beam shaping of a DT neutron tube generator. The interior of the beam shaping device is provided with a particle beam channel, and the particle beam channel is used for generating an initial neutron source through an incident proton beam. The beam shaping device comprises a value-added layer, a moderator, a filter layer, a reflecting layer, a collimator and a shielding layer, wherein the value-added layer, the moderator, the filter layer and the collimator are sequentially arranged from a target material to an outlet. And the axes of the particle beam channel, the value-added layer, the moderator and the collimator coincide. According to the beam shaping device, 14Mev high-energy neutrons from the DT neutron tube generator are shaped into hot / slow neutron beams meeting the BNCT treatment requirements, and impurities of fast neutrons and gamma rays are reduced to the maximum extent, so that the dosage precision and biological selectivity of treatment are effectively improved.

The invention relates to a method for detecting a coal seam interface while drilling, relates to the technical field of geological exploration, overcomes the limitation of a single physical field by using multi-modal fusion of electromagnetic waves, sound waves and gamma rays, remarkably improves the detection precision, greatly reduces the identification error of a thin coal seam compared with a traditional method, and improves the identification success rate of a complex structural region (fault and dirt band). Preliminary response within 1s is realized through underground edge calculation, decision lag is compressed to 1.5 s through ground cooperative processing, and leap of data real-time performance and predictive capacity is realized; the front 0.5-1.5 m prediction function gains time for track adjustment, and the risk of penetrating out of the coal seam is reduced. The multi-sensor redundancy design still keeps the signal-to-noise ratio not less than 20dB in a strong noise environment, the detection success rate is greatly improved when mud invasion is serious, and the environmental adaptability is high. The coal seam drilling rate is increased, invalid footage is reduced, the single well comprehensive cost is reduced, and economic benefits are remarkably improved.

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 relates to a method for detecting boron distribution in an oxidation corrosion product deposition layer. The total mass of boron in the oxidation corrosion product deposition layer is detected by utilizing an instantaneous gamma activation technology; the method comprises the following steps: obtaining a geometric boundary of a deposition layer of a corrosion product according to neutron photography, constructing a Compton cone in the geometric boundary obtained by neutron photography according to instant gamma rays generated by the oxidation corrosion product and Compton scattering information generated by the action of a Compton photography unit, and reconstructing the origin of the gamma rays; and carrying out pixelated image reconstruction by adopting a random origin set algorithm to obtain a distribution image generated by gamma rays so as to obtain the proportional distribution of the boron element in the oxidation corrosion product deposition layer. According to the obtained total boron element concentration and boron element proportion distribution, boron element concentration distribution in the oxidation corrosion product deposition layer is calculated, and the defects that only boron element distribution in the limited depth of the surface of the corrosion product deposition layer can be measured and internal element distribution information cannot be obtained in an existing method are overcome.

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 discloses a radiation shielding method and a radiation shielding body based on a multi-physics field synergistic effect, and the radiation shielding body is used for shielding a neutron-gamma mixed radiation field, and the radiation shielding method based on the multi-physics field synergistic effect comprises the steps: a first stage, absorbing neutrons and gamma rays at a radiation initial position through a first composite material; in the second stage, energy spectrum adaptive attenuation is carried out on the first residual radiation passing through the first stage through a second composite material, and the amount of the second composite material is gradually decreased in a gradient mode in the radiation propagation direction; and a third stage of performing path scattering on the second residual radiation passing through the second stage through a third composite material. According to the invention, the technical problem of insufficient shielding capability caused by difficulty in adapting to the dynamic shielding requirement of a neutron-gamma mixed radiation field when a traditional anti-radiation shielding body faces the neutron-gamma mixed radiation field generated in a BNCT treatment scene is solved.

A system and a method for a pulsed neutron logging tool. The pulsed neutron logging tool may include a pulsed neutron generator for generating one or more neutrons, one or more gamma ray scintillator detectors disposed in a detection area, a shielding block that separates the pulsed neutron generator from the one or more gamma ray scintillator detectors, and a shielding layer. The pulsed neutron logging tool may further comprise an information handling system communicatively connected at least in part to the pulsed neutron logging tool. The information handling system is configured to create a gamma ray spectrum from the one or more gamma rays detected by the one or more gamma ray scintillator detectors, remove a background from the gamma ray spectrum to form a peaks-only spectrum, and compare one or more peaks-only elemental standards to the peaks-only spectrum to determine an elemental weight and yield.

The invention belongs to the technical field of nuclear physics and particle accelerators, and relates to a high-precision wide-energy-spectrum neutron source target body structure applied to a spallation neutron source device. The method comprises the following steps: a tungsten target is adopted, and a 6cm thin target design is adopted; the cooling layer contains boron water and the like and can be used for cooling and slowing down neutrons; the moderation layer moderates the neutron energy spectrum to a thermal neutron energy region by using boron-containing water; the shielding layer is made of low-carbon steel and concrete to ensure radiation safety; the tail end of the neutron channel is connected with an experimental terminal; according to the thin target design, the energy resolution is improved, the energy resolution of neutrons below 100 keV is higher than 0.1%, and the energy resolution of neutrons below 1 MeV reaches 0.3%; the boron element reduces the gamma ray background; and the five neutron pore channels meet various requirements. The overall design realizes the effect required by the high-precision neutron experiment and improves the precision of the device.

The invention discloses a composite shielding collimator suitable for a complex mixed radiation field, belongs to the technical field of radiation shielding and measurement, and mainly solves the problems of low signal-to-noise ratio, high space background and mixed energy spectrum caused by the mixed radiation field of high-energy neutrons, gamma rays and the like in a fusion device and the problem that traditional equipment is heavy and difficult to flexibly adjust. The composite shielding collimator adopts a cylindrical shielding structure formed by aluminum oxide, boron-containing polyethylene, boron carbide and lead from outside to inside, and background interference and secondary radiation are remarkably inhibited by moderating and absorbing neutrons step by step and effectively shielding gamma rays; the neutron and gamma ray detector is integrally integrated on a rotatable supporting mechanism, unification of excellent radiation shielding performance and detection flexibility is achieved, and the neutron and gamma ray detector is mainly used for high-precision neutron and gamma ray diagnosis in complex radiation environments such as a magnetic confinement fusion device.

The invention provides a neutron energy spectrum measurement method for a boron neutron capture therapy beam, and belongs to the technical field of medical equipment. The sequence of the activated foils is optimized by adopting a Monte Carlo method; the activated foils are weighed and then stacked in a cadmium / aluminum detection box with the machining precision within 0.01 mm according to the sequence, and the center axis of the activated foils, the center axis of the detection box and the center axis of a beam are aligned through a treatment room positioning system; after irradiation under the nominal irradiation condition of the boron neutron capture therapy system, measuring the characteristic gamma ray full-energy peak net count of each activated foil by using a high-purity germanium gamma spectrometer, and calculating the mononuclear activation rate in combination with irradiation parameters; and processing group cross-section data through an NJOY program, and performing spectrum unfolding in combination with an initial spectrum simulated by Monte Carlo and an SAND-II algorithm. According to the method, a multi-material activated foil synchronous measurement technology is adopted, and the clinical applicability of boron neutron capture therapy beam quality control is remarkably improved through algorithm and data collaboration and activated foil sorting optimization.

The invention discloses a nuclear logging gamma-ray spectrum drift correction method based on multi-element characteristic peaks, and belongs to the technical field of nuclear geochemical logging. The method aims at solving the problems that due to the underground high-temperature and high-pressure environment, short-time measurement statistical errors and stratum lithology changes, drift of the relation between channel addresses and energy is caused, and energy spectrum analysis precision is affected. According to the key points of the technical scheme, the method comprises the following steps: preliminarily identifying characteristic gamma ray peak positions of four elements of H, Fe, Si and Ca; a real peak position is approached through interpolation secondary search; calculating zero-cut drift distances and gain change rates of Fe, Si and Ca peak positions by taking the H peak as a reference; weighting according to each peak standard error to obtain a final correction parameter; and re-graduating the energy spectrum by using the parameter to realize the automatic correction of the relationship between the channel address and the energy. The method is mainly used for improving the spectrum unfolding precision and the automatic processing capacity of the instant gamma-ray energy spectrum in geochemical logging, and is suitable for stratum element analysis in oil-gas exploration.

Systems and methods for generating synthetic borehole image logs include logging rate of penetration (ROP) data, resistivity data, and gamma ray data while drilling a borehole in a subsurface formation to generate logged data. The generating includes determining an effective dip angle of the subsurface formation along the borehole and generating a depth shift table based on the effective dip angle and a well deviation angle, the well deviation angle being between the borehole and a vertical reference. Datasets are generated based on the ROP data, resistivity data, and gamma ray data, the generated datasets having higher sampling rates than the logged data. Synthetic borehole images are generated based on the generated datasets and the depth shift table, and the synthetic borehole images are oriented with respect to a reference point of the borehole.

Tapered scintillator modules and detection devices having tapered scintillator modules in at least the end that contacts an optical sensor where the taper depends on the location of the scintillator module within the active area of the optical sensor is provided. Tapering of the scintillator modules may be close to the interface between the optical sensor and the module to minimize light leak to neighboring pixels at the interface while still allowing the detection device to retain high geometric efficiency and sensitivity to incident gamma rays since the distal end may not be tapered, which has a highest probability for gamma ray interaction based on Beer-Lambert law for photoelectric absorption.

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 control method and device of a material moisture online monitoring system and a storage medium, and relates to the technical field of material moisture monitoring, and the method comprises the steps: starting a neutron generator assembly, and starting a neutron detector assembly and a gamma detector when the starting duration of the neutron generator assembly is greater than or equal to the preheating preset duration; based on a detection result of the neutron detector assembly, determining an accumulated scattering neutron share of the detected material, and obtaining a corresponding target hydrogen density matched with the accumulated scattering neutron share from a preset association library; based on a gamma detector, counting the monitored gamma rays in a classified manner according to the pulse amplitude, generating a gamma-ray energy spectrum, and extracting a water hydrogen characteristic peak area from the gamma-ray energy spectrum; according to the target hydrogen density, the water-hydrogen characteristic peak area and the energy spectrum calibration coefficient of the gamma-ray energy spectrum, the curing hydrogen ratio is determined; and determining the free water content of the detected material according to the cured hydrogen ratio. According to the invention, through dual-mode cooperative detection, the problem of low accuracy of moisture monitoring is solved.

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.

A radiation dose quantification method and system, the method comprising: detecting, with one or more detectors with respective sensitive volumes, gamma-rays emitted as a result of capture of neutrons by a composition in a subject subjected to an irradiation program, the composition comprising one or more thermal neutron capture agents, the neutrons having been generated by non-elastic collisions between a primary beam of particles and nuclei in the subject, wherein the particles consist of any one or more of protons, deuterons, tritons and heavy ions, the irradiation program comprises at least one period of irradiation with a beam duration that includes beam-on periods and beam-off periods; applying at least one predefined energy window or filter configured to accept only detection events in the one or more detectors resulting from gamma-rays with an energy indicative of selected gamma-rays arising from the capture of thermal neutrons by the one or more thermal neutron capture agents, wherein the thermal neutrons are neutrons with energies below approximately 0.4 eV; applying a timing window configured to reject or ignore detection events in the one or more detectors resulting from at least prompt gamma-rays produced in non-neutron capture events; and determining the radiation dose of neutron radiation received by the subject during the irradiation program from at least the accepted detection events or determining a dose map of the radiation received by the subject from at least the accepted detection events.

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 belongs to the technical field of flexible ray protective clothing, and discloses medical flexible ray shielding protective clothing and a preparation method thereof. A medical flexible ray shielding protective garment comprises a shielding material, flexible rubber and a garment material, the shielding material is equally distributed in small capsule cabins of the flexible rubber, and the small capsule cabins are distributed in the thickness direction of the flexible rubber for 3-10 times; the clothing material is attached to the flexible rubber loaded with the shielding material to manufacture the clothing. The novel integrated ray protection suit provided by the invention adopts a lead-free shielding material, has a relatively good shielding effect on gamma rays and X rays, is soft in material, light in weight and non-toxic and harmless to a human body, can be widely applied to military industry, medical science, other ray protection laboratories and the like, and has a wide application value.

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.

The invention relates to a personal dosimeter for neutron and photon mixed radiation detection and a detection method, the dosimeter comprises a base, an upper cover and three groups of detection assemblies, and the base is provided with three grooves which are distributed in parallel and respectively accommodate a first detection assembly, a second detection assembly and a third detection assembly. The first detection assembly and the second detection assembly each comprise a neutron absorber with grooves formed in the upper portion and the lower portion and a 6Li thermoluminescence detector pair and a 7Li thermoluminescence detector pair, and separated measurement of the dose of thermal neutrons, medium-high energy neutrons and gamma rays is achieved. The third detection assembly comprises a neutron moderator and a solid track detector. Separation measurement of neutrons with different energies is realized through track density difference. The upper cover is provided with a measuring window, and tissue equivalent materials with different mass thicknesses are adopted and correspond to the dose depth of Hp (10) and the dose depth of Hp (3). Through combination of multi-channel reading and correction coefficient calculation, dose evaluation of gamma rays, thermal neutrons and fast neutrons on different tissue depths can be realized. The device is compact in structure, and is suitable for personal dose monitoring in a complex radiation environment.

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.