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60 results about "Neutron activation" patented technology

Neutron activation is the process in which neutron radiation induces radioactivity in materials, and occurs when atomic nuclei capture free neutrons, becoming heavier and entering excited states. The excited nucleus often decays immediately by emitting gamma rays, or particles such as beta particles, alpha particles, fission products, and neutrons (in nuclear fission). Thus, the process of neutron capture, even after any intermediate decay, often results in the formation of an unstable activation product. Such radioactive nuclei can exhibit half-lives ranging from small fractions of a second to many years.

Synthesis, compositions and methods for the measurement of the concentration of stable-isotope labeled compounds in life forms and life form excretory products

Stable isotope labeling and neutron activation to measure biological functions are provided, as are the use and method of adding a chemical monitor to correct for neutron flux to sample vials prior to the addition of sample is presented, and the use of stable isotopes as a chemical bar code for vials and other items. Methods are provided also for measuring glomerular filtration rate and glomerular sieving function in a subject, and for measuring other physiological functions.
Owner:BIOPAL

Fusion reactor tungsten divertor structure design based on high temperature fused salt cooling

The present invention discloses a fusion reactor tungsten divertor structure design based on high temperature fused salt cooling. The fusion reactor tungsten divertor structure design comprises a tungsten surface pair plasma material and tungsten and lanthanum alloy heat sinks. The tungsten and lanthanum alloy heat sinks comprises a tungsten and lanthanum alloy heat sink 1 and a tungsten and lanthanum alloy heat sink 2. The tungsten and lanthanum alloy heat sink 1 is a half pipe with a C-shaped cross section, and the tungsten and lanthanum alloy heat sink 2 is a half pipe with a round angle and a semi-rectangle-shaped cross section. The tungsten surface pair plasma material is connected to the tungsten and lanthanum alloy heat sink 1, and the tungsten and lanthanum alloy heat sink 1 is connected to the tungsten and lanthanum alloy heat sink 2 to form a whole pipe. through the effective combination of tungsten and lanthanum alloy materials and a high-temperature fused salt cooling agent, the fusion reactor tungsten divertor structure design based on high temperature fused salt cooling is provided to adapt to a fusion reactor high-flux neutron irradiation environment, the heat bearing capacity can reach a 10-20MW / m2 steady-state thermal load, the structural material neutron activation is low, the , nuclear waste processing after component retirement is relatively easy, and the improvement of fusion reactor power generation economical efficiency is facilitated.
Owner:INST OF PLASMA PHYSICS CHINESE ACAD OF SCI

Microspheres comprising therapeutic and diagnostic radioactive isotopes

One aspect of the present invention relates to a microsphere impregnated with a radioisotope that emits therapeutic ß-particles and a radioisotope that emits diagnostic gamma radiation; wherein the atomic number of the first radioisotope is not the same as the atomic number of the second radioisotope. In one preferred embodiment, the microsphere is composed of glass impregnated with 90 Y as the source of the therapeutic ß-emissions and 98 Au as the source of the diagnostic gamma emissions. Another aspect of the present invention relates to the preparation of a microsphere impregnated with a radioisotope that emits therapeutic ß-particles and a radioisotope that emits diagnostic gamma radiation; wherein the atomic number of the first radioisotope is not the same as the atomic number of the second radioisotope. In one preferred embodiment, a glass microsphere containing 90 Y and 198 Au is prepared by neutron activation of a glass microsphere comprising glass, 89 Y and 197 Au. Another aspect of the present invention relates to administration to a mammal of a therapeutically effective amount of microspheres impregnated with a ß-emitting radioisotope and a gamma emitting radioisotope; wherein the atomic number of the first radioisotope is not the same as the atomic number of the second radioisotope. In one preferred embodiment, said microspheres are administered to the patient through a catheter.
Owner:BIOSPHERE MEDICAL INC

Method for detecting coal quality composition on conveying belt and device thereof

The invention provides a method for detecting coal quality composition on a conveying belt and a device thereof; the device comprises a shielding case arranged on the conveying belt, a neutron generator and a gamma-ray detector, and an analysis processing system, wherein a closed space is formed in the shielding case, and the inner side of the shielding case is provided with a neutron reflector; the neutron generator and the gamma-ray detector are arranged inside the shielding case and positioned below the conveying belt, and neutron slowed bodies are filled among the conveying belt, the neutron generator and the gamma-ray detector; the analysis processing system is arranged outside the shielding case and is connected with the gamma-ray detector, and is used for obtaining the signals output by the gamma-ray detector to carry out energy spectrum analysis and calculate the content of coal quality composition and industrial analysis data. Through the embodiment of the invention, neutron activation prompt fission gamma-ray technology is adopted without sampling and sample making processes, and the content of coal quality composition can be obtained in time; therefore, the problem that the coal quality analysis data is hysteretic is solved.
Owner:CHANGSHA KAIYUAN INSTR

Movable box type combined shielding system

The invention discloses a movable box type combined shielding system which comprises a container, an in-box radiation shield, an out-box radiation shield and a photon shielding plate. A radioactive source generating device is arranged in the container; the space between the radioactive source generating device and the inner wall of the container is fixedly filled with the in-box radiation shield; the outer wall of the container is detachably covered with the out-box radiation shield; the photon shielding plate is arranged on the outer wall of the container in a sliding mode and used for sliding to an active area when the out-box radiation shielding body is detached to shield active area rays. According to the movable box type combined shielding system, the radioactive source generating device can run and be transported in the container; when the radioactive source generating device runs, the in-box radiation shield and the out-box radiation shield can be combined to shield high-dose radiation generated when the radioactive source generating device runs; when a container body is transported, the in-box radiation shield and the container body are detached, and the photon shielding plate moves to the active area to shield rays generated by neutron activation of a container active area structure material.
Owner:中科瑞华原子能源技术有限公司

Pulsed neutron generated prompt gamma emission measurement system for surface defect detection and analysis

A method of determining structural defects in a component that utilizes neutron activation of a solution having the ability to penetrate small cracks on the surface of a material via capillary absorption that produces a discernable prompt gamma release of a defined energy when exposed to a neutron pulse. The intensity of the gamma rays produced at the desired energy at a user controlled position on the surface is used to determine the crack location, length and depth.
Owner:WESTINGHOUSE ELECTRIC CORP

Vitamin C wastewater electrolysis oxidation pretreatment method

The invention discloses a vitamin C wastewater electrolysis oxidation pretreatment method, and belongs to the technical field of wastewater treatment. Vitamin C wastewater is gradually degraded by three steps. Firstly, atomized low-foam activators contact with the vitamin C wastewater along with bubbles bubbled by a bubbling machine, so that contact area is enlarged, and surface activation of thevitamin C wastewater is facilitated. Secondly, the wastewater is subjected to neutron bombardment by a pulsed neutron activation device, energy is provided for organic matters in the wastewater, and internal electrons of the wastewater are jumped into an excited state. Thirdly, the wastewater activated by the first two steps is subjected to ultimate electrolysis oxidation by an electrolysis oxidation reactor. After graded activation, final electrolysis oxygenolysis efficiency can be greatly improved. In conclusion, the method is good in pretreatment effect and creates good conditions for subsequent biological enhancement processes.
Owner:NANJING UNIV

Sample irradiation device for neutron activation

The invention discloses a sample irradiation device for neutron activation. The sample irradiation device comprises a controller, a speed reducer, an irradiator, a vacuum tank, a compressed air tank and a gamma ray detector, wherein the speed reducer and the irradiator are arranged up and down and are fixedly connected; the irradiator is respectively connected with the vacuum tank and the compressed air tank; the gamma ray detector is fixedly connected with the irradiator; the speed reducer, the irradiator and the gamma ray detector are respectively and electrically connected with the controller. The sample irradiation device for the neutron activation, disclosed by the invention, is used as one of important and key components of an online neutron activation sample transmission and analysis system, has the functions of reducing the speed of rapidly transmitted sample boxes, hovering activated samples, particularly irradiated overdose samples, in reactor pool water outside a reactor activity zone for cooling and discharging water accumulated at the bottom part of an irradiation pipe, is more beneficial for radiation protection of environment and staff and is good in running stability and running safety.
Owner:INST OF NUCLEAR PHYSICS & CHEM CHINA ACADEMY OF

Neutron activation sample fast transmission device

The invention discloses a neutron activation sample fast transmission device which includes a commutator, a sample injector, a sample receiver, an irradiator, a waste storage device, a glove box, a vacuum tank, a gas tank, an irradiation monitor, and a controller. The irradiation monitor includes a detector and a measuring instrument. The sample injector, the sample receiver, the irradiator, the waste storage device and the glove box are connected with the commutator through a sample conveying pipe. The commutator, the sample receiver, the irradiator and the glove box are connected with the vacuum tank through a gas circuit. The commutator, the sample injector, the sample receiver and the glove box are connected with the gas tank through a gas circuit. The detector is fixedly connected with the irradiator. The commutator, the sample injector, the sample receiver, the irradiator, the waste storage device, the glove box and the measuring instrument are electrically connected with the controller. The neutron activation sample fast transmission device has the functions of sample transmission, irradiation, storage, measurement, discarding, dose monitoring and over-irradiated sample suspended cooling and the characteristics of compact structure and lower noise. Moreover, the device has good stability and safety.
Owner:INST OF NUCLEAR PHYSICS & CHEM CHINA ACADEMY OF

Radioactive microsphere and radioactive filler composition

The invention provides a radioactive microsphere and radioactive filler composition. Provided is a radioactive microsphere including glass having a structure represented by a formula Ca3Si2O7 and yttrium oxide contained in the glass. The radioactive microsphere has sphericity of from 0.71 to 1, and is radioactive after being activated by neutron irradiation. The radioactive microspheres are delivered to target tissues for neutron activation to generate radiation to treatment tumors, the radioactivity of the microspheres disappears along with time, and finally, the microspheres can be dissolvedand absorbed through bone tissues.
Owner:PLATINUM OPTICS TECH

Online detection method for energy-saving environment-friendly laterite-nickel ore smelting shaft furnace smelting slag

The invention discloses an online detection method for energy-saving environment-friendly laterite-nickel ore smelting shaft furnace smelting slag, belonging to the field of ferronickel production. The method comprises the following steps of: cooling the shaft furnace slag by a granulator; after the temperature is below 60 DEG C, conveying the shaft furnace slag into a neutron activating element analyzer by a belt conveyor to perform online detection on the shaft furnace slag; analyzing and processing a detection signal by a processor to obtain the element content; transmitting the data of element content to related enterprises to receive the data for use, directly conveying the furnace slag to a furnace slag storage yard by the belt conveyor. The shaft furnace slag is detected and analyzed by an online detection device, so the method has the advantages of high analysis speed, quick feedback, strong representativeness, little overall error, safety and reliability and high degree of automation, and does not need extra testers or extra furnace slag chemical analysis medicines. Through the energy-saving environment-friendly online detection device of shaft furnace smelting slag of laterite-nickel ore, the recovery rate of metal nickel can be obviously improved, and the production cost is lowered.
Owner:FUSHUN HANKING DRI CO LTD

Elemental analysis device combined with neutron-activation instant and delayed gamma rays

The invention discloses an elemental analysis device combined with neutron-activation instant and delayed gamma rays, and belongs to the field of the application of nuclear technology. The elemental analysis device is used for measuring an inelastic scattered instant characteristic gamma energy spectrum of a sample in a combinational manner by using a fast neutron source and a lanthanum bromide detector, measuring a neutron captured instant characteristic gamma energy spectrum in the combinational manner by using a slow neutron source and a high-purity germanium detector and finally measuringa neutron-activation delayed characteristic gamma energy spectrum in the sample by using a sodium iodide detector. Relative to a conventional neutron-activation elemental analysis device, the elemental analysis device provided by the invention not only utilizes instant characteristic gamma rays generated by neutron activation, but also collects delayed characteristic gamma rays; relative to the instant rays, delayed rays have a small quantity, however, are not interfered by a neutron, and further, seldom has the superposition of characteristic peak positions of gamma rays; a specific element is conveniently and accurately analyzed and calculated. A fast neutron and a slow neutron irradiate the sample respectively to increase an irradiation time, and the generation efficiency and the collection efficiency of inelastic scattered gamma rays and neutron captured gamma rays are improved.
Owner:JILIN UNIV

Transmission type cement raw material on-line neutron activated sulfur alkali ratio analysis device and analysis method

The invention relates to a transmission type cement raw material on-line neutron activated sulfur alkali ratio analysis device and an analysis method. A measuring device is a gamma detector fixed between an upper belt and a lower belt, a neutron source is placed above the upper belt and above a cement raw material, neutrons are downwards irradiated on the cement raw material on the belt to generate action with nucleus in the cement raw material, the gamma detector transforms the received ray into a pulse signal and transmits the pulse signal to a multi-channel energy spectrum analyzer to be processed, the multi-channel energy spectrum analyzer uploads effective information to an upper computer, and the upper computer calculates the sulfur alkali ratio of the cement raw material according to the corresponding formula. The sulfur alkali ratio finally obtained by calculation is a ratio relation between SO3 content and the sum of K2O content and Na2O content, so the sulfur alkali ratio is not influenced by the total amount of the cement raw material on the belt; the overall shielding protection of the instrument adopts a two-layer structure, the inner layer is lead and the outer layer is polyethylene, so the use amount of the lead is reduced, and the cost and the weight of the instrument are reduced; and a detector shielding body adopts a two-layer structure, the outer layer is polyethylene and the inner layer is a cadmium plate, so the influence on the gamma detector by the neutrons is minimized, and the analysis precision of the instrument is improved.
Owner:DANDONG DONGFANG MEASUREMENT&CONTROL TECHCO

Transmission commutator for activated sample

The invention discloses a transmission commutator for an activated sample. The transmission commutator comprises a motor, a cylinder, a lead screw, a sample loader and a support, wherein the sample loader is in a cylinder shape; the cylinder is horizontally and fixedly arranged on the support; the motor is fixedly connected with one side of the cylinder in the X axial direction; the lead screw and the sample loader are arranged in the cylinder; the circle center line of the sample loader and the axial lead of the lead screw are both superposed with the X axial lead of the cylinder; one end of the lead screw is in sliding connection with the wall of the cylinder through a bearing; the other end of the lead screw penetrates through the cylinder and is fixedly connected with a shaft of the motor; and the lead screw penetrates through the center of the sample loader and is in sliding connection with the sample loader. The transmission commutator for the activated sample, disclosed by the invention, is used as one of important and key parts in a transmission system for neutron activated samples; in-pile radiation of sample boxes and transfer of the sample boxes towards multiple working places after radiation can be realized by adopting one commutator, and the compactness of the transmission device for neutron activated sample boxes and the transmission efficiency of the sample boxes are favorably improved, and operation stability and the safety are high.
Owner:INST OF NUCLEAR PHYSICS & CHEM CHINA ACADEMY OF

Method for gradually approximating scale gamma energy spectrum high-energy region based on peak shape fitting

The invention discloses a method for gradually approximating a scale gamma energy spectrum high-energy region based on peak shape fitting. According to the method, a standard gamma source and gamma rays generated by neutron activation characteristic substances are gradually adopted for calibration; a simple energy spectrum is adopted to scale a low-energy section, then a low-energy section scale result is used to estimate a high-energy section peak position, a peak shape fitting method is adopted to determine a peak center, an energy scale range is continuously expanded, an interested high-energy section is gradually approached, and finally a channel address interval corresponding to the interested high-energy section is obtained. Compared with a traditional method that professionals recognize manual scales after multiple samples are activated at a time and complex gamma energy spectra are obtained, the method provides a set of self-adaptive processes and algorithms, automatic scale isachieved, the requirement for operators is reduced, and an application scene of neutron activation analysis is greatly expanded.
Owner:INST OF NUCLEAR PHYSICS & CHEM CHINA ACADEMY OF +1

Speed reducer for conveying of pile irradiation sample

The invention discloses a speed reducer for conveying of a pile irradiation sample. The speed reducer comprises a sealing chamber, a speed reducing pipe, an exhaust pipe, a transmission mechanism anda plurality of spring mechanisms. The speed reducing pipe, the exhaust pipe, the transmission mechanism and the spring mechanisms are arranged in the sealing chamber; the speed reducing pipe and the exhaust pipe are arranged vertically; the two ends of the speed reducing pipe and the lower end of the exhaust pipe penetrate out of the sealing chamber and airtightly and fixedly connected with the sealing chamber; the upper end of the exhaust pipe is communicated with the upper part of the speed reducing pipe; the spring mechanisms are arranged on the speed reducing pipe; the transmission mechanism is arranged on the speed reducing pipe and the exhaust pipe; and a plurality of strip-type openings are vertically formed in the speed reducing pipe. The speed reducer for the conveying of the pileirradiation sample, as one of important and critical components of a neutron activation sample conveying system, can effectively reduce the speed of a quickly moving sample box, has the characteristics of compact structure and good sample box speed reducing effect, has a protective effect on the safety of the sample box and a conveying device and operates safely and reliably.
Owner:INST OF NUCLEAR PHYSICS & CHEM CHINA ACADEMY OF

Target material for neutron line generating device

The invention relates to a target material for a neutron line generation device, which is high in strength, good in radiation damage resistance and small in radioactivity after being activated by neutrons, foaming can be inhibited, the heat dissipation performance of the target material is improved, and the service life of the target material is prolonged. According to the target material for the neutron line generation device, the target material comprises an acting layer and a heat conduction layer, the acting layer can act with incident particle lines to generate neutron lines, the heat conduction layer supports the acting layer, the heat conduction layer is made of a metal-based graphene nano composite material, and the metal-based graphene nano composite material is a metal-based graphene nano composite material. The thermal conductivity of the metal-based graphene nano composite material is improved by more than 20% relative to that of the metal matrix.
Owner:NEUBORON THERAPY SYST LTD

Automatic sample injecting device for neutron activation

The invention discloses an automatic sample injecting device for neutron activation, which includes a controller, a commutator, a sample injector I, a sample injector II, a sample injector III, a gas tank, an air compressor, and a stand. The sample injector I and the sample injector III, the commutator and the sample injector II, and the gas tank are respectively and fixedly arranged in the upper, middle and bottom layers of the stand. The sample injector I, the sample injector II and the sample injector III are connected with the commutator through a sample conveying tube. The commutator, the sample injector I, the sample injector II and the sample injector III are connected with the gas tank through pipes. The gas tank is connected with the air compressor through a pipe. The commutator, the sample injector I, the sample injector II, the sample injector III and the air compressor are electrically connected with the controller. The automatic sample injecting device for neutron activation has the characteristics of compact structure and less vibration and noise during operation. With the device, a large batch of samples can be injected in an automatic and orderly manner under programmed control. The device has good stability and safety.
Owner:INST OF NUCLEAR PHYSICS & CHEM CHINA ACADEMY OF

Marker selection method for oil field logging

The invention discloses a marker selection method for oil field logging. The method comprises the following steps of (a) selecting elements capable of participating in neutron activation treatment, and calculating element factors S of the selected elements according to the following formula (1): S=[theta]*[sigma]*[beta]*[gamma] / M(1); and (b) sorting the elements in a sequence from large S factors to small S factors according to the determination result in the step a, and primarily selecting the elements which are sorted in the front; then performing gamma ray interference elimination in the primarily selected elements, i.e., only remaining the elements with the large S factors in the elements with the characteristic gamma ray signal mutual interference; and regarding the finally left elements as marked elements. The invention provides a brand-new marker selection method; and through cooperation with the trace analysis, the flow rate of produced liquid in each target position under a well and the proportion of water to crude oil in the produced liquid can be accurately reduced. Meanwhile, the normal operation state of a horizontal well cannot be damaged, system errors can be effectively reduced, and the accuracy and reliability of the measurement result are improved.
Owner:四川松云科技有限公司

Accelerator-driven neutron activator for brachytherapy

A neutron activator for neutron activation of a material, the neutron activator being configured to produce neutrons from an interaction with a proton beam (7), the neutron activator comprising:a neutron source comprising a metallic target (1), anda Beryllium first reflector-moderator (4) peripheral to the neutron source and comprising a neutron activation area (10) configured to accommodate the neutron source and the material to be activated, the neutron activation area (10) of the first reflector-moderator (4) comprising a bore configured to accommodate the neutron source.
Owner:ADVANCED ACCELERATOR APPLICATIONS SA

Device for detecting French chalk content in flour

The invention discloses a device for detecting French chalk content in flour, and belongs to the field of nuclear technology application. The device utilizes a neutron activation principle to irradiate the flour with neutrons with energy of 14 MeV, short-lived radionuclide 28Al and 24Na are generated by the reaction between the neutrons and 28Si and 24Mg which are the main elements in French chalk(Mg3[Si4O10](OH)2), and by measuring delayed characteristic gamma rays released by the 28Al and 24Na, whether or not the flour contains French chalk is determined and the specific French chalk content is calculated. The device can penetrate the surface of the tested flour to measure the French chalk content of the inside, compared with chemical detection, the speed is fast, no sampling is needed,and the device can be directly installed on a transport belt, is suitable for real-time online detection, and has high detection precision, low detection limit, long-term measurement stability and strong anti-interference ability.
Owner:JILIN UNIV +1

A sensor for on-line detection of tritium content in liquid lead-lithium alloy

The invention provides a sensor for on-line detection of tritium content in liquid lead-lithium alloy. The sensor comprises parts such as a sample chamber, a reference chamber, an electrode, a valve, a work gas tank and a vacuum pump. The diffusion and seepage of tritium in a wall surface of the sample chamber is used, so that the liquid lead-lithium alloy and the tritium in the sample chamber reach the balance; further, the tritium content in the liquid lead-lithium alloy is obtained through measuring the tritium content in the sample chamber. The influence of radioactivity of neutron active products in the liquid lead-lithium alloy on the tritium content is reduced through installing the reference chamber. The sensor provided by the invention has the advantages that (1) the on-line detection of the tritium content in the liquid lead-lithium alloy can be realized; (2) the carrying of extracted tritium in the liquid lead-lithium alloy by carrying gas is avoided, and the detection process is relatively simple; (3) the measurement is directly performed in the sample chamber, and the tritium loss and the stain are reduced; (4) the gamma radiation field in the liquid lead-lithium alloy can be synchronously detected. The sensor is applicable to the on-line detection of the tritium content in a fusion reactor liquid lead-lithium cladded layer loop.
Owner:HEFEI INSTITUTES OF PHYSICAL SCIENCE - CHINESE ACAD OF SCI

Nuclear emergency dose card and nuclear emergency dose measuring method

PendingCN108535760AQuick Category ManagementControl Radiation Dose LevelsDosimetersDosimetry radiationRadiation damage
The embodiment of the invention provides a nuclear emergency dose card and a nuclear emergency dose measuring method. The nuclear emergency dose card comprises a main body (1), a measuring unit (2), and an identification unit (3). The identification unit (3) is arranged at the upper surface of the main body (1); an opening is formed in the lateral surface of the main body (1); and the measuring unit (2) is inserted into the main body (1) through the opening. The measuring unit (2) is used for measuring the neutron personal dose by a metal neutron activation sheet. Therefore, the personal doseof radiation can be recorded or traced; quick classification management of the personnel is implemented effectively; the radiation dose level received by the first responder is controlled; and the necessary radiation dosimetry information is provided for follow-up radiation damage treatment.
Owner:NAT INST FOR RADIOLOGICAL PROTECTION & NUCLEAR SAFETY CHINESE CENT FOR DISEASE CONTROL & PREVENTION +2

System and method for real time on-stream analysis of oil sands composition

A method for real time on-stream analysis of oil sands composition is disclosed comprising the steps of detecting a moisture content of an oil sands stream using a microwave transmission analyzer, detecting an elemental composition of the oil sands stream using a prompt gamma neutron activation analyzer and calculating a content of hydrocarbons, clays and sands in the oil sands stream. The total clay amount in the oil sands stream is based on the detected gamma spectra of several elemental components of the oil sands stream, such as sodium, magnesium, potassium, calcium and iron.
Owner:SACRE DAVEY INNOVATIONS INC

Storage Device for Reactor Neutron Activation Samples

The invention discloses a storage device of reactor-neutron activation samples. The storage device comprises a controller, a storer, a speed reducer and a shielding box, wherein the controller is arranged at the shielding box side, the storer is fixedly arranged in the shielding box, the speed reducer and the shielding box are fixedly arranged from top to bottom, the speed reducer is connected with the storer by a sample delivering pipe which is vertically arranged, and the controller is respectively and electrically connected with the storer and the speed reducer. As one of important and keyparts of a conveying system of the reactor-neutron activation samples, the storage device of reactor-neutron activation samples disclosed by the invention can realize effective speed reduction for sample boxes with fast movement, has the characteristics of compact structure, accurate rotational positioning of a bracket, ideal speed-reducing effect of the sample boxes and high sample-conveying efficiency, has a function of conveying the sample boxes into an irradiator for irradiation again, is applicable to automatic reception and storage of large-batch irradiation samples, and is good in stability and safety of operation.
Owner:INST OF NUCLEAR PHYSICS & CHEM CHINA ACADEMY OF

Neutron activation energy spectrum processing method, device, equipment and medium

The invention provides a neutron activation energy spectrum processing method which comprises the following steps: acquiring original energy spectrum data which comprises original channel address data, original acquisition time data, original neutron flux data and original characteristic peak data; obtaining standard channel address data according to the original channel address data; obtaining standard acquisition time data according to the original acquisition time data; obtaining standard neutron flux data according to the original neutron flux data; obtaining standard spectrum peak offset data according to the original characteristic peak data; and obtaining standard energy spectrum data according to the standard channel address data, the standard acquisition time data, the standard neutron flux data and the standard spectrum peak offset data. According to the neutron activation energy spectrum processing method disclosed by the invention, energy spectrum data can be standardized before neutron activation analysis and quantitative calculation.
Owner:HEFEI GOLD STAR MECHATRONICS TECH DEV CO LTD

Digital imaging plate for neutron photography nondestructive testing of radioactive sample and radioactive sample neutron photography nondestructive testing method

The invention discloses a digital imaging plate for neutron photography nondestructive testing of a radioactive sample, a manufacturing method of the digital imaging plate and a radioactive sample neutron photography nondestructive testing method. The digital imaging plate comprises a substrate and a digital imaging plate imaging film arranged on the substrate. The digital imaging plate imaging film includes a cured adhesive bonded to the substrate, pure metal powder and barium fluorobromide crystals, wherein the pure metal powder and the barium fluorobromide crystals are dispersed in the adhesive. The barium fluorobromide crystals in the digital imaging plate can be continuously exposed through secondary particles released by continuous decay of pure metal powder activated by transmission neutrons in the digital imaging plate, so that recorded neutron beam intensity distribution information of a transmission sample is recorded in the barium fluorobromide crystals; a digital imaging plate scanner is used for scanning the digital imaging plate to obtain neutron photographing detection imaging of the radioactive sample, the process of transferring a neutron conversion screen to a darkroom and making the neutron conversion screen closely contact with a film or the digital imaging plate is omitted, and the precision of the imaging data intensity of the digital imaging plate is improved.
Owner:CHINA INSTITUTE OF ATOMIC ENERGY

Pure beta ray corrying safe microball and its preparation

The present invention relates to a glass microphere with pure beta-rays capable of producing action for curing carcinoma after having been activated and its preparation process. It is made up by using glass microsphere with pure beta-rays and anticorrosive coating layer applied onto external surface of the glass microsphere by adopting sol-gel method. The advantages of said invention lies in that the radioisotope in not easy to be penetrated into blood, the external physiological simulation liquid soaking test shows that the resolution of its correspondent nuclein is reduced by 1-2 orders of magnitude as compared with resolution of nucleic of microsphere without anticorrosive coating layer, it has no radioactive pollution, and its chemical stability is high. Said invention is simple in preparation process, its operation is safe and reliable, can be extensively used for radiotherapy to cure carcinoma.
Owner:TONGJI UNIV
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