81 results about "Radiogenic Isotopes" patented technology

Disclosed are thermotherapeutic compositions for treating disease material, and methods of targeted therapy utilizing such compositions. These compositions comprise a) stable single domain magnetic particles; b) magnetic nanoparticles comprising aggregates of superparamagnetic grains; or c) magnetic nanoparticles comprising aggregates of stable single magnetic domain crystals and superparamagnetic grains. These compositions may also comprise a radio isotope, potential radioactive isotope, chemotherapeutic agent. These methods comprise the administration to a patient's body, body part, body fluid, or tissue of bioprobes (energy susceptive materials attached to a target-specific ligand), and the application of energy to the bioprobes so as to destroy, rupture, or inactivate the target in the patient. Energy forms, such as AMF, are utilized to provide the energy. The disclosed methods may be useful in the treatment of a variety of indications, including cancers, diseases of the immune system, central nervous system and vascular system, and pathogen-borne diseases.

An isotope seeding system that controls the release of radioactive seeds for treatment of cancerous cells during cancer treatment procedures. The isotope seeding system comprises at least one seed that is chargeable with radioactive isotopes. At least one dissolvable web netting may alternatively be positioned about the at least one seed, and a seed deployment assembly is utilized for delivering the at least one seed, with or without the dissolvable web netting, into an organism's tissue, to surround cancerous cells. The seed deployment assembly includes an elongated cannula, a hub assembly and an obturator. The hub assembly includes an initial inner diameter at its proximal end and an operable length between the proximal end of the hub assembly and the proximal end of the cannula, the ratio of the initial inner diameter relative to the operable length being in the range of 0.075 to 0.175, to preclude against jamming of the at least one seed, with or without the at least one dissolvable web netting wrapped thereabout, within the hub assembly and / or to further preclude against inadvertent migration of such seeds from the web netting when such netting is utilized.

This invention relates to a method and apparatus for separation of rare stable or radioactive isotopes from their atomic or molecular isobars in mass spectrometry (MS). In the present invention, the approach taken to removing atomic isobars utilizes a high transmission device for decelerating ions in combination with low energy reactions, such as ion-molecule reactions or near resonant electron transfer, in RF ion guides. The isobar is selectively depleted by electron transfer or other reactions between negative ions and gaseous targets in pressurized RF ion guides at low energies. The energy is controlled in such a way as to prevent reaction of the ion of interest while inducing reactions with the undesired isobar interference. The technique is of particular relevance to accelerator mass spectrometry (AMS) for which it allows substantial reductions in the necessary terminal voltage. The effect is to allow reductions in the size and cost of AMS installations.

Disclosed herein is a prompt gamma-ray detection apparatus for analyzing chemical materials using femtosecond pulse laser-induced neutrons, which can be effectively used in the nondestructive inspection of various materials, such as metals, coal, cement, radioactive materials and the like as well as explosives and chemical materials, and which can provide better measurement results for the analysis of basic materials, and a method of measuring prompt gamma-rays using the apparatus. The prompt gamma-ray detection apparatus is advantageous because it can non-destructively analyze the elements in a chemical sample using a femtosecond pulse laser-induced neutron generator that solves the problems of an atomic reactor for research or a radioactive isotope as a neutron radiation source.

The invention discloses an agent plate for testing hepatocarcinoma and a preparation method and the application thereof. The agent plate is composed of a rigid plate and an agent strip attached to the rigid plate, and the agent strip is formed by sequentially and closely splicing absorbent filter paper, a pyroxylin membrane, a glass fibre membrane and a sample adsorption glass fibre membrane from top to bottom, wherein a gold-labeled anti-mouse AFP monoclonal antibody is absorbed by the glass fibre membrane; an agglutinin coated detection line is arranged at one end of the pyroxylin membrane, which is adjacent to the glass fibre membrane, and a goat anti mouse IgG coated contrast line is arranged at the other end which is adjacent to the absorbent filter paper; and the lower end of the sample adsorption glass fibre membrane is provided with a row of loading holes. The agent plate for testing hepatocarcinoma has the advantages that a fluorescence microscope, an Elisa tester and other expensive instruments are not needed, and the agent plate is much more suitable for field test; the agent plate is safer since radioactive isotopes, TMB and other harmful substances or chemical substances are not needed in testing processes; test results can be preserved for a long time; and the operation of the agent plate is easy and fast, and the agent plate can be operated by a single person.

The present invention provides a nuclear medicine imaging apparatus and image data generation method that achieves restarting of the generation of projection data and at an early stage while monitoring a variation of count values for detecting an occurrence of non-permissible body movement of a patient. The image processing apparatus consistent with the present invention detects a pair of gamma-rays successively emitted from an object with a radioactive isotope through a pair of detector modules in a data detecting unit. A data processing unit and an incident direction calculating unit in the image processing apparatus respectively calculate a gamma-ray detection position and a gamma-ray incident direction based on the acquired detection signals. A projection data generating unit in the apparatus generates monitoring projection data based on each count value of the detection signals in correspondence to the gamma-ray detection position and the gamma-ray incident direction. A projection data monitoring unit calculates a body movement index of the object by comparing count values of the monitoring projection data that are generated in each of two preferably adjoining monitoring periods. A system control unit generates an alarm signal for performing repetition of the monitoring projection data when the body movement index exceeds a threshold value and displays the alarm signal on a display unit.

A label-free biochemical detection method reinforced by utilizing local surface plasma is characterized in that the label-free biochemical detection method comprises the steps as follows: (1) preparing an LSPR detection chip according to a detected object; (2) selecting a specific biological molecule to activate the chip according to the detected object, and testing the spectrum reference value of the chip by a spectrum test system; (3) leading in a to-be-detected sample for detection, and obtaining a spectrum curve by test; and (4) judging whether the to-be-detected sample contains the detected object by analysing the spectral peak movement state of the spectrum, so as to quickly detect the detected object with high sensitivity and without a label, meanwhile, the array chip is used for realising high-efficiency and multi-channel detection. The method of the invention does not need complex equipment and does not use radioactive isotope, enzyme or fluorescence as a label, has the remarkable characteristics of low cost and high sensitivity, and can realise array chip. The method provides a simple and practical new method for fast detection of biochemical molecule.

The invention discloses a method for determining a Guanling cattle MyoDI gene core promoter by using a dual-luciferase report gene. The method comprises the following steps: constructing a recombinant vector containing a Guanling cattle MyoDI gene promoter full-length fragment and a subcloning fragment; culturing skeletal muscle growth-related cells and planking; preparing a promoter recon / liposome mixture, and carrying out transfection on the cells obtained in the step (2); carrying out dual-luciferase activity detection on the transfection cells obtained in the step (3) by using the dual-luciferase report gene. The method has the advantages of high sensitivity, fastness in detection speed and low cost and does not need radioactive isotopes and the like; as a used pGL3-Basic report gene does not comprise the promoter and an enhancer, the expression of the luciferase report gene can be used for detecting the starting activity of inserted promoters and comparing the intensity of the promoters, and further a core promoter region is preliminarily determined.

The invention belongs to the field of nuclear technology application and particularly relates to a wide-energy-spectrum BF3 long neutron counter, the average energy response of the long neutron counter is 3.01 cm<2>, and the average relative deviation is 6.87%. An MCNP5 program is used for controlling a simulation calculation result to be within a statistical error range of 0.78 percent; the relative detection efficiency of the long neutron counter at the position 150 cm away from a point source is simulated, the relative detection efficiency is 2.05*10<-3> to 2.62*10<-3> within the energy range of 1 KeV to 15.2 MeV, the average relative detection efficiency epsilon is 2.31*10<-3>, and the average deviation is 6.84%. The long neutron counter overcomes the problems that in the prior art, the energy lower limit of a neutron counter is high, the energy response is sharply reduced in a range of above 5 MeV, the energy response flat range is not long enough and the like, and the requirements of high-flux-rate monitoring of most accelerator neutron sources or neutron fluence rate calibration of radioactive isotope neutron sources can be met.

The invention relates to a preparation method of an adsorbent containing SnO2 / Sb2O5. According to the method, SbCl3 with a stable chemical property and low toxicity is taken as a Sb source, sodium thiosulfate pentahydrate, namely SnCl4, is utilized as a Sn source, and a SnO2 / Sb2O5 binary composite oxide is prepared. The preparation method comprises the following steps of oxidizing Sb<3+> as Sb(V) in a non-water system taking alcohol as a solvent by adopting the combination of H2O2 oxidation and ultraviolet irradiation, further carrying out hydrolytic precipitation on Sb(V) and Sb<4+> by utilizing a small amount of water introduced by utilizing H2O2 solution as a reactant, and forming a binary SnO2 / Sb2O5 composite oxide. The method provided by the invention has the advantages that the hydrolyzing speed of Sb<3+> is slow, the generation of the Sb2O3 is effectively controlled, the Sn / Sb2O5 binary composite oxide with the Sb<3+> oxygenation efficiency being 100% is obtained, the adsorbent can remove the radioactive isotope Co ions and a complex thereof and stable isotope Co ions and a complex thereof, and the adsorptive property of the SnO2 / Sb2O5 binary composite oxide and pure Sb2O5 obtained by the introduction of Sb is improved by 200 times.

A method and system for classifies an unknown sample that contains either a first radioactive isotope, a second radioactive isotope, or a mixture of the first and second radioactive isotopes. Input vectors representative of a training set of samples for a first isotope class and a second isotope class are received. A multivariate classification model is constructed based on the received input vectors. Data is received corresponding to the unknown sample. First and second probabilities that the unknown sample respectively belongs to the first isotope class and the second isotope class are calculated. Based on the first and second probabilities, the unknown sample is classified as either the first radioactive isotope, the second radioactive isotope, or a mixture of the first and second radioactive isotopes.

A method and apparatus for isolating and purifying a 213Bi radioactive isotope from an 225Ac source using a primary column and a primary sorbent which preferentially retains 225Ac over 213Bi when exposed to a compatible solvent in combination with a secondary column having a secondary sorbent which retains 213Bi when exposed to a mixture of the compatible solvent and 213Bi. A “compatible solvent” is a solvent which will preferentially remove 213Bi radioactive isotopes from a primary sorbent without removing 225Ac radioactive isotopes, and then allow 213Bi radioactive isotopes removed from the primary sorbent to be retained on a secondary sorbent, without having to dilute or otherwise chemically or physically modify the compatible solvent in between exposure to the primary and secondary sorbents.

A method of identifying radioactive components in a source comprising (a) obtaining a gamma-ray spectrum from the source; (b) identifying peaks in the gamma-ray spectrum; (c) determining an array of peak energies and peak intensities from the identified peaks; (d) identifying an initial source component based on a comparison of the peak energies with a database of spectral data for radioactive isotopes of interest; (e) estimating a contribution of the initial source component to the peak intensities; (f) modifying the array of peak energies and peak intensities by subtracting the estimated contribution of the initial source component; and (g) identifying a further source component based on a comparison of the modified array of peak energies with the database of spectral data. Thus a method for identifying radioactive components in a source is provided which does not rely on comparing template spectra with an observed spectrum.

A bismuth-213 generator comprising an insoluble composition having the general formula Zr(Phosponate)x(HPO4)2−x.nH2O, wherein x is between 0 and 2; and n is the number of waters of hydration; and wherein cations of radioactive isotopes selected from radium, actinium and combinations thereof are immobilized on the composition. The value of x may be between about 0.2 and about 1. The phosphonate may be n-phosphonomethyl-miniodiacetic acid (PMIDA), wherein x may be between about 0.1 and about 1.9. The phosphonate may be one or more phosphonate having the formula:H2O3P—(CH2)a—N—((CH2)bCO2H)—((CH2)cCO2H),wherein a, b, and c are numbers from 1 to 3 that may or may not be equal. The value of x may also be between about 0.1 and 1.9.

The invention discloses a pressure testing method for a radioactive isotope carrier. The method comprises the following steps of: coating a certain quantity of radioactive isotope carriers with cotton gauze, and putting into a high-pressure reaction kettle which is resistant to the pressure of 10-40 MPa; putting chemical reagents which can produce gases through chemical reactions into the high-pressure reaction kettle in an isolating way; sealing the high-pressure reaction kettle, mixing the at least two types of chemical reagents, and raising the pressure of a system to a target pressure; when the pressure is constant, preserving pressure for 3-5 hours; and safely deflating to the normal pressure in a ventilation kitchen, opening the high-pressure reaction kettle, taking the radioactive isotope carriers out, and measuring the breakage rate, density and granularity by experimenting. The pressure testing method disclosed by the invention has the characteristics of low equipment cost and easiness, convenience and practicability for operating.

The invention relates to a method and system for the treatment of radioactive wastes produced as a consequence of the operation of nuclear power plants with pressurized water reactors and boron reactivity regulation accompanied by the simultaneous production of environmentally acceptable substances of, for example, borax, calcium-magnesium borates, boron acid and sodium hydroxide solutions.As a result of the radioactive waste treatment method and system according to the invention, the following products are obtained: borax with an environmentally acceptable content of radioactive isotopes that contain only the cesium isotopes with a maximum total concentration of 800 Bq in one kilogram of borax; calcium, magnesium and / or calcium-magnesium borates with an environmentally acceptable content of radioactive isotopes; boron acid solution with an environmentally acceptable content of radioactive isotopes; sodium hydroxide solution containing only the cesium isotopes with a maximum total concentration of 800 Bq in one kilogram of sodium hydroxide; and radioactive waste containing under 5 g / l of boron acid.

A material in the form of an alveolar monolith consisting of a matrix of an inorganic oxide with a hierarchical and opened porosity comprising macropores, mesopores and micropores, said macropores, mesopores and micropores being interconnected, and nanoparticles of at least one metal cation exchange inorganic solid material being distributed in said porosity.A method for preparing this material and a method for separating a metal cation notably a cation of a radioactive isotope of a metal such as cesium using this material.

The invention discloses a radioactive isotope wastewater treatment system, and belongs to the technical field of radioactive isotope wastewater treatment. Key points of the technical scheme are as follows: the system comprises a separation tank for separating solid wastes in wastewater, a plurality of radioactive isotope wastewater attenuation tanks, a plurality of waste storage chambers, a stirring device and a collecting device; the stirring device is arranged in the separation tank; an inclined plane sedimentation structure is arranged in the separation tank and is used for settling solid wastes crushed by the stirring device, so that the crushed solid wastes can enter into the collecting device; the radioactive isotope wastewater attenuation tanks are all provided with drainage pipes for drainage, the radioactive isotope wastewater attenuation tanks are connected with the separation tank through water inlet pipes; and after processed wastewater is detected to be qualified, the drainage pipes are opened to discharge wastewater in the radioactive isotope wastewater attenuation tanks. The radioactive isotope wastewater treatment system can achieve the purpose of synchronously treating radioactive wastewater and solid wastes, is suitable for treating radioactive isotope wastewater, and can effectively reduce the pollution of solid waste and wastewater to the environment.

A liquid reactant metal alloy includes at least one chemically active metal for reacting with non-radioactive material in a mixed waste stream being treated. The reactant alloy also includes at least one radiation absorbing metal. Radioactive isotopes in the waste stream, including any fast neutron emitting isotopes alloy with, or disperse in, the chemically active metal and the radiation absorbing metals are able to absorb a significant portion of the radioactive emissions associated with the isotopes. A transmutation target fraction is included for absorbing fast neutrons and a transmutation emission absorbing fraction is provided for absorbing emissions that result from the absorption of a fast neutron by the transmutation target fraction. Non-radioactive constituents in the waste material are broken down into harmless and useful constituents, leaving the alloyed radioactive isotopes in the liquid reactant alloy. The reactant alloy may then be cooled to form one or more ingots in which the radioactive isotopes are effectively isolated and surrounded by the radiation absorbing metals. These ingots comprise the storage products for the radioactive isotopes.

A method for obtaining 225AC from 225Ra having the steps of assembling a column having an inorganic stationary phase; priming the column to immobilize 226Ra 225Ra and natural decay products therefrom; immobilizing the 226Ra, 225Ra, 224Ra, and natural decay products therefrom onto a stationary phase within the column; and eluting the column containing the 225Ra with an aqueous sulfate solution to obtain a milking effluent that contains 225AC. Also provided is a method for obtaining pure 225AC from its isotope parents, the method comprising assembling a column having a stationary phase comprising an inorganic material; priming the column with the isotope parents to immobilize 225Ac, and natural decay products of 225AC; immobilizing the 225Ac, and natural decay products therefrom onto the stationary phase within the column 226Ra, 225Ra, 224Ra; and eluting the column containing the 225AC to obtain an effluent that contains the isotope parents.

The invention relates to a method and a system for separating and concentrating radionuclides in radioactive waste liquid by utilizing a reverse osmosis membrane. In the method and system of the present invention, a specific membrane material having a high decontamination factor for radionuclides in the context of higher non-radioactive ion concentrations is employed. The method comprises the following steps: 1) providing the specific membrane material with a high decontamination factor for radionuclides under the background of higher non-radioactive ion concentration; and 2) enabling radioactive waste liquid to flow through the surface of the membrane material so as to separate and concentrate radionuclides. The method and the system can effectively separate and concentrate radionuclidesin the radioactive waste liquid and solidify the radionuclides, particularly have an excellent removal effect on radioactive isotopes Cs and Co, greatly reduce the amount of secondary wastes, simplifythe process and improve the safety.

The invention discloses a method for producing radioactive isotopes based on a commercial pressurized water reactor irradiation target. The radioactive isotopes are produced by using the commercial pressurized water reactor irradiation target; specifically, the operation of producing the radioactive isotopes by using the commercial pressurized water reactor irradiation target comprises the following steps of: S1, during shutdown of a commercial pressurized water reactor, mounting the irradiation target in a guide pipe of a fuel assembly; S2, enabling the irradiation target to enter a reactor core along with the fuel assembly for irradiation, and carrying out reaction in a neutron field environment in the reactor to generate target radioactive isotopes; and S3, after the reactor is shut down again, taking out the irradiation target, and extracting the target radioactive isotopes. Due to the application of the technology, a new method is provided for the production of radioactive isotopes, the neutron field environment in the pressurized water reactor can be more fully utilized, and the economic performance of the pressurized water reactor is improved.

The invention provides an advanced dynamic forecasting method applying an isotope to tracing a rock mass water flowing channel. The advanced dynamic forecasting method comprises the following steps that pilot drilling is carried out in front of tunneling to form a logging well, and a filter tube is arranged in the logging well; a radioactive isotope tracer is put into the filter tube, a seepage principle is used for permeating water flows, and the flow velocity and the flow rate of water are measured; and an inspection logging well is drilled in front of the water flows, the distribution condition of the water flowing channel is reversely obtained through the determination of the isotope concentration and recording of the water quantity in the inspection logging well, and the feed relationof water of the water flowing channel is determined through the change of the isotope concentration of water flowing into the logging well.

A continuous dynamic positron emission tomography (PET) assembly for imaging a target region of a subject. The assembly includes a radioactive tracer isotope injector configured to administer a radioactive isotope into the subject and a scintillator crystal configured to absorb ionizing radiation from the subject and emit scintillator light. The scintillator crystal undertakes the absorption substantially at the same time of the start of administering the radioactive isotope. The assembly also includes a photo detector in communication with the scintillator crystal, wherein the photodetector is configured to detect the emitted scintillation light as input and provide electrical signals as output. The assembly further includes a signal digitizing circuitry converting the output electrical signals into digital data. Moreover, the assembly includes a processor configured to receive the digital data and implement a model to convert the digital data into a three dimensional, tomographic image reconstruction.

The invention relates to the field of continuous sampling, detection and sample returning of an online ash meter for a coal preparation plant, and discloses a continuous sampling, detection and sample returning device of an online ash meter. The device is composed of a chute, a sampling port, an upper screw conveyer, an upper screw conveying channel, a lower screw conveying channel, a wear-resistant polyethylene measuring tube, a radioactive isotope online ash content meter, a lower screw conveyer, a return baffle and the like. Coal flow enters the upper spiral conveyor through the sampling port and is conveyed to the discharging end of the upper spiral conveyor, the coal flow falls into the lower spiral conveyor under the gravity action of a coal flow coal sample and is conveyed into the wear-resistant polyethylene measuring pipe, and a detector and a radioactive source of the ash content meter are located at the upper end and the lower end of the wear-resistant polyethylene measuring pipe respectively, and the measured coal flow returns to the chute through the chute discharge hole and the return baffle. The device can eliminate the influence of external factors such as steel wires in the adhesive tape, the compaction degree and the thickness of a coal seam and the like on ash content measurement, and can remarkably improve the measurement precision and the accuracy of an online ash meter.

The invention relates to the field of radioactive element wastewater treatment, and provides an amorphous antimony oxide for adsorbing radioactive Sr-90 and Co-60 and a preparation method of the amorphous antimony oxide in order to solve the problems that an existing organic ion exchange agent has a poor effect and shorter service life when being used for treating low-concentration nuclear radioactive wastewater, and an antimony pentoxide adsorbent prepared in the prior art has the smaller adsorption capacity for Sr-90. The preparation method comprises the following steps that 1) antimony butter and hydrochloric acid are taken as raw materials, weighed and mixed to obtain a mixed solution; 2) the mixed solution is oxidized in a water bath condition and then is mixed and hydrolyzed with a large amount of water, filtering separation is carried out to obtain a hydrolysis product, and the amorphous antimony oxide for adsorbing the radioactive Sr-90 and Co-60 is obtained after drying. The amorphous antimony oxide for adsorbing the radioactive Sr-90 and Co-60 and the preparation method of the amorphous antimony oxide have the advantages that the preparation method is concise and efficient, and a part of raw materials can be recycled; the prepared amorphous antimony oxide has huge specific surface area and a disordered structure, and has a very strong adsorbing effect on Sr-90, Co-60and other radioactive isotopes.

The invention discloses an engine internal flow field measuring system and a measuring method thereof. The method comprises the steps of preparing a grain of a solid rocket engine through employing aradioactive isotope raw material, generating a large amount of high-speed high-temperature fuel gas after the grain is ignited to form a flow field, generating plume through the spraying of a sprayingpipe, and enabling radioactive isotope particles to release gamma rays when the radioactive isotope particles flow along with the flow field, and using the gamma ray dynamic collector for collectingreleased gamma rays to measure the dynamic characteristics of the internal flow field of the solid rocket engine. The measuring system uses radioactive isotopes as tracer particles to achieve non-contact measurement of the internal flow field of the solid rocket engine, and compared with a traditional measuring method, the original structure of the solid rocket engine does not need to be damaged,the problem that a traditional measuring method disturbs an internal flow field can be avoided, and compared with an existing numerical calculation method, the defect that the numerical calculation result is insufficient in accuracy can be overcome.

The invention belongs to the field of radioactive isotope preparation, and relates to a device for extracting gaseous iodine in a loop for producing iodine-125. The device comprises a turntable, an extraction mechanism and a fixed seat; the extraction mechanism is mounted in the turntable, one ends of two symmetrically arranged gas nozzles are fixedly connected with the turntable and are butted and communicated with a first gas channel in the extraction mechanism, the other ends of the gas nozzles are inserted into the fixed seat and are respectively butted and communicated with two second gas channels in the fixed seat; and the two second gas channels, the two gas nozzles and the first gas channel form a closed circulating gas loop for gas to enter and exit, and an iodine separation material is arranged in the first gas channel. The extraction mechanism can be plugged on the loop device as an independent structure. The extraction mechanism can prevent iodine-125 generated in the loop from participating in circulation loop irradiation. During recovery, only the extraction mechanism needs to be leached, so that the processes of xenon-125 gas transfer, liquid nitrogen freezing, target cylinder cutting and the like are reduced, the operation process is simplified, the device can be repeatedly used, and the cost is reduced.

The invention provides a manufacturing method of a radioactive isotope battery. The method comprises the steps that the inner wall of a transparent container is coated with a powdery luminescent material, a radioactive material is put into the container, rays generated by decay of the radioactive material excite the luminescent material to emit radiation light to the outside of the container, theradiation light irradiates a photoelectric conversion device, and energy in the radiation light is converted into electric energy. By using the technical scheme of the invention, gaseous tritium isotope or solid tritiated titanium powder is selected as a radioactive material, widely exists in earth atmosphere and nature, and is convenient to store and transport, so that the manufacturing process of the radioactive isotope battery is greatly simplified, the output voltage of the electric energy generated through conversion of the radiation material can reach 0.8 V, the high voltage can be provided through the series connection and parallel connection of a plurality of modules, the output energy is stable, the service life of the radioactive isotope battery is prolonged, the manufacturing cost is reduced, and a foundation is laid for wide commercial application of the radioactive isotope battery.