87 results about "Thermal neutron detector" patented technology

A continuous neutron spectrum real-time detection system comprises a plurality of spherical-shell polyethylene moderation layers, a plurality of spherical-shell thermal-neutron detector systems, an electronics system, a computer system, an input power supply interface, a signal output interface, a display panel and a switch; and after neutrons with different energies enter the detection system, the neutrons are moderated by different moderation layers to thermal neutrons to be finally detected by the detector system of one layer, a pulse signal is transmitted to the electronics system, the electronics system analyzes and outputs relevant signals according to signals inputted by different detection layers, finally the computer system outputs a corresponding energy value according to different signals outputted by the electronics system and draws and records an energy spectrum. The continuous neutron spectrum real-time detection system is small in size and capable of precisely measuring neutron energy spectrum on one position.

[Problems to be Solved] A phoswich radiation detector, which can easily discriminate between detection signals on gamma rays and thermal neutrons, and which can selectively acquire signals on thermal neutrons, is provided.

[Means to Solve the Problems] In a phoswich radiation detector having two scintillators and discriminating between thermal neutrons and gamma rays, the detector comprises a scintillator for detecting thermal neutrons, such as LiCaAlF₆:Eu, which has a light yield of more than 1500 photons/neutron, and a scintillator for detecting gamma rays, which has a permeable end on a shorter wavelength than the light emission wavelength of the thermal neutron scintillator. The scintillator for detecting gamma rays is characterized by being either an organic solid scintillator, such as a plastic scintillator, which does not contain a total amount of 10 mol % or more of elements selected from ⁶Li, ¹⁰B and Gd, or an inorganic single crystal scintillator, such as lithium glass (containing ⁶Li and Ce) or BGO, which has an effective atomic number Z_eff of 30 or larger and which does not contain a total amount of 10 mol % or more of elements selected from ⁶Li, ¹⁰B and Gd.

A thermal neutron detector and method employ Gd-containing nanoscintillators. Thermal neutron radiation is detected by observing scintillation events from the nanoscintillators.

The invention discloses a method and instrument for controllable source neutron logging during drilling. The method comprises the steps that a pulse neutron source on a drill collar is started and quantitative high-energy neutrons are emitted to a stratum in a pulse mode; the number of thermal neutrons with the speed reduced by the stratum is measured through a long spacing detector and a short spacing detector which are arranged on the drill collar respectively, wherein the thermal neutrons are scattered back to a well hole; according to the number, measured through the two spacing detectors, of the thermal neutrons, the macroscopic capture cross section sigma of the thermal neutrons and the porosity phi of the stratum are obtained; the stratum water saturation Sw is obtained according to the macroscopic capture cross section of the thermal neutrons and the porosity phi. The instrument comprises the pulse neutron source, a detection unit, a signal processing and data analyzing unit and a power module used for supplying power for the detection unit and the signal processing and data analyzing unit. The thermal neutrons are detected through the long spacing <3>He thermal neutron detector and the short spacing <3>He thermal neutron detector, two sets of parameters including the porosity and the macroscopic capture cross section of the thermal neutrons and are obtained, and therefore the measurement of the water saturation and the porosity of the stratum with a relatively low degree of mineralization is achieved. Due to the use of the pulse neutron source, damage, caused by a radioactive source, to human and the environment is eliminated.

The invention discloses a controllable-neutron three-detector element well logging device and method, which specifically relate to the field of oil and natural gas exploration. The device uses a D-T controllable neutron source, a near He-3 neutron detector, a LaBr3 crystal gamma detector, and a super far He-3 thermal neutron detector. The two He-3 neutron detectors collect the time spectrum of neutrons and the total count of neutrons. The LaBr3 gamma detector collects inelastic and capture gamma time spectrums, and measurement information is uploaded to ground equipment through a telemetry pipe nipple of the instrument. The method includes the following steps: first, processing the inelastic gamma energy spectrum, calculating the inelastic gamma yield of elements, and calculating the dry weights of Si, C and other elements according to the inelastic yield of elements, the near-to-super far neutron counting ratio and other information; and then, processing the capture gamma energy spectrum, calculating the capture yield of elements, and calculating the contents of elements which can be measured by the capture gamma energy spectrum, such as Ca, S and Fe, according to the contents of elements determined by inelastic gamma and the capture yield.

The invention discloses a thermal neutron detector and a manufacturing method thereof. The thermal neutron detector comprises a microchannel plate, wherein the microchannel plate comprises a plurality of glass tubes forming a microchannel, and a film layer containing thermal neutron absorbing material is coated on the inner wall of the microchannel. Higher detecting efficiency, favorable spatial resolution and better thermal neutron/gamma suppression ratio can be realized through coating the film layer containing the thermal neutron absorbing material on the inner wall of the microchannel by using a mature film coating technology without changing the glass components of the glass tubes of the microchannel plate, therefore, the preparation process of the microchannel plate can not be influenced, and the common microchannel plate capable of being obtained commercially can be utilized.

The invention discloses a fast neutron detection method, which is used for detecting fast neutrons with X-rays, and comprises the following steps: passing the fast neutrons through a neutron slowing body to absorb the X-rays and slow the fast neutrons into thermal neutrons; and detecting the thermal neutrons by using a thermal neutron detector to obtain the information on the fast neutrons. The invention also discloses a method for identifying substances by using photoneutrons, a method for identifying substances by using X-rays and the photoneutrons, and a neutron detector. The neutron detector comprises the neutron slowing body which is suitable for absorbing the X-rays therein and slowing the fast neutrons into the thermal neutrons; and the thermal neutron detector which is suitable for detecting the thermal neutrons to obtain the information on the fast neutrons. In the invention, the interference of the X-rays with the fast neutron measurement can be eliminated by arranging the neutron slowing body, so the accuracy of the neutron measurement is improved. And as the attenuation information of the X-rays and the attenuation information of the neutrons, which are different, are obtained at the same time, the capability of identifying detected objects is improved.

This invention describes a remmeter that is based on the use of an assembly comprising two or more different-sized hydrogenous moderators, each hydrogenous moderator incorporating a hydrogenous spectroscopic fast neutron detector and a thermal neutron detector in order to provide more accurate neutron dosimetry across a wide range of neutron energies (thermal neutrons to >15 MeV) in a form factor that is lighter than conventional remmeters. The new remmeter utilizes the principle of spectral dosimetry, where the energy or energy distribution of the incident neutrons is first measured and then this energy information (along with the measured fluence) is used to establish the dosimetric quantity using the various fluence-to-dose conversion curves (e.g. H*(10) (ICRP (1997)), NCRP-38 (1971)). Using the method of spectral dosimetry, the large variation in response in these curves as a function of neutron energy (especially over the region 1 keV to 1 MeV) is largely mitigated through the use of the energy and fluence information, and the appropriate fluence-to-dose conversion curve to calculate the dose.

The invention belongs to the technical field of neutron detection, and provides a concrete emptying detection method, device, and terminal equipment. The method comprises following steps: reading thethermal neutron counting rate N1 of a first thermal neutron detector and the thermal neutron counting rate N2 of a second thermal neutron detector, calculating the counting rate ratio of N1 to N2, wherein the distance between the first thermal neutron detector and a neutron source is smaller than the distance between the second thermal neutron detector and the neutron source; obtaining the thickness of a steel plate that covers the surface of concrete, based on the thickness of the steel plate, finding the corresponding relationship between the counting rate ratio and concrete emptying depth;and based on the corresponding relationship, determining the concrete emptying depth corresponding to the counting rate ratio. The method has the advantages that a large amount of tedious operation isreduced, and the efficiency on measuring the concrete emptying depth is largely improved.

This invention relates to a chlorin spectrometry logging method for measuring under-well saturation moisture content during the brine layer oil injection period in oil exploration. It adopts thermal neutron detector and gamma detector to measure the thermal neutron and elastic gamma information generated in the reaction of the neutron emitting source and earth layer and it calculates the apparent porosity and water saturation in the pay through the measurement the difference between the neutron and the neutron gamma relative saturation fresh water or oil earth layer. So it overcomes the influence of the mud and frame in the earth layer and the double difference method can improve the responding accuracy in the measurement of the ground water mineralization rate.

The invention provides a measuring instrument for concrete void detection, the measuring instrument is applicable to the technical field of neutron detection, and the measuring instrument comprises aneutron source, a processing unit, a first thermal neutron detector and a second thermal neutron detector; the neutron source is used for transmitting fast neutrons to concrete covered with a steel sheet; the first thermal neutron detector and the second thermal neutron detector are used for obtaining heat neutron counting rate N1 and heat neutron counting rate N2 at two locations, with differentdistances from the neutron source, on the steel sheet covering the surface of the concrete; the processing unit is configured to calculate the counting rate ratio of heat neutron counting rate N1 to heat neutron counting rate N2; the processing unit is further configured to obtain the thickness of the steel sheet covering the surface of the concrete, according to the thickness of the steel plate,a corresponding relationship between the counting rate ratio and a concrete void depth is found, and the concrete void depth corresponding to the counting rate ratio is determined according to the corresponding relationship. The measuring instrument saves a lot of cumbersome operation and greatly improves the efficiency of actual concrete void depth measurement.

A combined thermal neutron detector and gamma-ray spectrometer system, including: a detection medium including a lithium chalcopyrite crystal operable for detecting thermal neutrons in a semiconductor mode and gamma-rays in a scintillator mode; and a photodetector coupled to the detection medium also operable for detecting the gamma rays. Optionally, the detection medium includes a ⁶LiInSe₂ crystal. Optionally, the detection medium comprises a compound formed by the process of: melting a Group III element; adding a Group I element to the melted Group III element at a rate that allows the Group I and Group III elements to react thereby providing a single phase I-III compound; and adding a Group VI element to the single phase I-III compound and heating; wherein the Group I element includes lithium.

The invention discloses a neutron detector. The neutron detector comprises a neutron moderating body and a thermal neutron detector, wherein the neutron moderating body is suitable for absorbing X rays passing through the neutron moderating body and moderating fast neutrons into thermal neutrons; and the thermal neutron detector is suitable for detecting the thermal neutrons to acquire information about the fast neutrons. Through the neutron moderating body, interference of the X rays to fast neutron measurement can be eliminated, so that the neutron measurement accuracy is improved. The identification capacity of a detected object is improved by simultaneously acquiring two types of different attenuation information of the X rays and the neutrons.

The present invention provides a cellular thermal neutron detector, comprising: a cellular structure comprised of one or more hollow regular hexagonal prism-shaped cellular units, wherein a neutron absorbing material is coated on an inner side of a pipe wall of each of the cellular units. Since the neutron-sensitive cellular structure is employed, the present invention can perform thermal neutron detection without using the scarce nuclide 3He, and effectively reduce the manufacture costs of the thermal neutron detector. Further, the present invention has characteristics such as a reduced or eliminated neutron detecting dead zone.

The invention discloses a method for detecting the hollow depth of concrete under a steel shell. The method comprises the steps as follows: step 1, establishing a hollow depth calibration curve library: by changing hollow depth 1 between a steel plate and a concrete simulation standard block, thickness h of the steel plate and water content omega of the concrete simulation standard block, calibrating the hollow depth 1 by a thermal neutron detector to obtain the hollow depth calibration curve library, wherein the hollow depth calibration curve library comprises multiple hollow depth calibration curve units with different water contents, and each hollow depth calibration curve unit comprises three hollow calibration curves with different steel plate thicknesses; step 2, arranging detectionpoints; step 3, selecting and determining hollow depth calibration curves; step 4, measuring and determining the hollow depth. The hollow depth calibration curves are established, effects of water content of concrete on the hollow depth are fully considered, and different calibration curves are adopted for different steel plate thicknesses and water content of concrete, so that the detection of the hollow depth is more accurate and rapid.