78 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.

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.

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 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.

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 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.

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 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 discloses an evaluation method for the effect of concrete for preventing pollution of band-discharge waste liquid. The evaluation method comprises a concrete antifouling effect test method based on a gas permeation method, an ion permeation method and a non-radioactive isotope diffusion depth method. The evaluation method integrates various influence factors and can evaluate the effect of preventing the concrete from being polluted by the waste liquid.

The invention discloses a fuel rod fission product release simulation device and a using method thereof. The simulation device comprises a heating furnace, a crucible and a fuel rod simulator, whereinthe fuel rod simulator is used for simulating a cladding and a pellet of a prototype fuel element; the crucible is used for supporting the fuel rod simulator and providing a gas circulation flow channel at the same time, the crucible can contain liquid melt when the fuel rod simulator is molten, and the melt is prevented from damaging the heating furnace; and the heating furnace is used for heating the fuel rod simulator. The invention provides a fission product release characteristic experimental device which does not contain radioactive isotopes and has a structure similar to that of a realfuel rod in physical and chemical processes for a fission product release characteristic experiment, and the fission product release characteristic experimental device can be used for researching release characteristics of various fission products with different reactor types and different serious burnup accidents.

The invention discloses an open channel automatic flow measurement method based on a dilution method. Tracers such as salt, fluorescent dye and radioactive isotope are adopted, a section is put at theupstream of the open channel water flow with a certain turbulence degree; an instruction is sent out through an A/D single-chip microcomputer, a tracer agent feeding device automatically feeds traceragents, the tracer agents are fully mixed with water, the concentration of water flow is measured through a detection point concentration meter device concentration meter on the downstream detectionsection and then converted into flow, and the method is high in measurement precision, wide in application range, capable of saving time and labor and wide in application prospect.