345 results about "Radiogenic nuclide" patented technology

The invention relates to a particulate material consisting of a low density radiation-tolerant glass and a radionuclide incorporated into the low density glass or coated on the low density glass, the glass having a density of less than 2.5 g / cm3, processes for its production and a method of radiation therapy utilising the patentable material.

An apparatus for producing a radionuclide includes a target chamber including a beam strike region for containing a liquid and a condenser region for containing a vapor. A particle beam source is operatively aligned with the beam strike region, and a lower liquid conduit communicates with the beam strike region. The condenser region is disposed above the beam strike region in fluid communication therewith for receiving heat energy from the beam strike region and transferring condensate to the beam strike region. The lower liquid conduit transfers liquid to and from the beam strike region. In operation, the target chamber acts as a thermosyphon that is self-regulating in response to heat energy deposited by the particle beam source. A portion of the liquid expands into the lower liquid conduit prior to boiling. After boiling begins, a vapor void is created above the liquid and an evaporation / condensation cycle is established, with additional liquid being displaced into the lower liquid conduit.

A method for preparing a radioactive surface source for radiotherapy is disclosed. The method comprises: (a) providing a structure having a surface; (b) positioning the structure in a flux of at least one radionuclide so as to collect atoms of the at least one radionuclide on or beneath the surface; and (c) treating the surface such that the atoms are intercalated into the surface but allowed to recoil out of the surface upon radioactive decay. In various exemplary embodiments of the invention the method further comprises coating the surface by at least one layer of polymeric material, such that the atoms are collected into the polymeric material.

The invention discloses a method for preparing radioactive <124>I ions. The preparation method comprises the following steps: a, taking aluminium oxide powder and tellurium dioxide powder in a mass ratio of 1:18-22, uniformly mixing the powder, and pressing the obtained mixture into a tellurium target with a thickness of 50-60 mg / cm<2>; b, placing the prepared tellurium target in a circular accelerator, and irradiating the tellurium target 2-3 h by Te (p, n) <124>I, wherein the incident p particle beam intensity is 18-20 mu A, the energy is 18.5-20 MeV, and the angle of incidence is 6-10 DEG; meanwhile, cooling the tellurium target by using water in the process of irradiating, and after the irradiating is completed, placing the tellurium target to cool 4-6 h; c, placing the tellurium target in a quartz distillation tube of a destructive distillation device to distill, meanwhile, controlling the temperature to 750 DEG C so as to heat the tellurium target, so that radioactive <124>I ions are escaped, and collecting the radioactive <124>I ions. The problems that radionuclide <124>I prepared in the prior art is low in yield and low in recovery rate are solved.

The invention relates to a pyrochlore type high-entropy oxide solidified body and a preparation method thereof. The high-entropy oxide solidified body has a pyrochlore structure, and the chemical formula is RE2M2O7, wherein RE is a rare earth element, and M is a transition metal element. The pyrochlore-type high-entropy oxide solidified body of the invention has excellent chemical stability. Radioactive nuclides of different valence states and types can be solidified in crystal lattices of a high-entropy oxide base material, deep geological disposal is facilitated, , and the system of solidification treatment of base materials for radioactive nuclear waste is enriched. The method is low-cost, is simple and feasible and has a wide application range. The process is high in efficiency and good in safety, and is expected to be applied to the technical field of radioactive nuclear waste treatment.

The invention belongs to the technical field of the microorganism, and in particular to a treatment method of soil contaminated by radioactive nuclide uranium or cesium. The invention adopts a bar screen, a double-plate screen and a spiral screen to screen the soil contaminated by uranium or cesium. The soil particles with the particle size more than 0.25mm are clean soil particles, the soil particles with the particle size less than 0.25mm are soil contaminated by uranium or cesium; and the soil particles with the particle size less than 0.25mm are mixed with active acidithiobacillus ferrooxidans for treatment, and the settlement is clean soil after filtration, the filtrate is transferred and mixed with active sulfate reducing bacteria for treatment, then the uranium or cesium is precipitated and can be recovered through filtering separation, and the water can also be recovered. The invention has the advantages of simple operation and low cost, and realizes the rapid and efficient removal of the uranium or cesium in the slightly contaminated soil.

A method of suppressing deposition of radionuclides on components of a nuclear power plant comprises forming a ferrite film by contacting a first chemical including iron (II) ions, a second chemical for oxidizing the iron (II) ions to iron (III) ions, and a third chemical for adjusting the pH of a processing solution containing a mixture of the first and second chemicals to be 5.5 to 9.0 with the metal member surface in a time period from a finishing stage in decontamination step of removing contaminants formed on the surface of metal member composing the nuclear power plant, and suppressing deposition of radionuclides on the metal member by the ferrite film.

The invention relates to the technical field of radiation detection and provides a nuclide recognition device using lanthanum bromide to measure radioactive aerosol in the air. The nuclide recognition device comprises an aerosol detecting system, an air flow circuit system and an electric system. The aerosol detecting system comprises a gas sampling circuit, a lanthanum bromide detector and an automatic paper feed mechanism. The lanthanum bromide detector is fixed in a cavity formed by the gas sampling circuit. The automatic paper feed mechanism is disposed at the outlet of the gas sampling circuit. The gas sampling circuit comprises a rotary drum and filter paper fixed at two ends. The nuclide recognition device has the advantages that the lanthanum bromide detector is used to detect the gamma ray generated by the radioactive nuclide, nuclide recognition capability of the device is increased greatly, and environmental background can be removed easily.

The present invention relates to a method and apparatus for simultaneous quantification of the amounts of one or more radioactive nuclides within arbitrary regions on a surface where these nuclides have been deposited, adsorbed or fixed. These radioactive nuclides serve as markers on compounds that typically have been incorporated into tissue sections or into larger biological molecules that by various mechanisms have been bound to chemical substances on this surface. The method is especially well suited for DNA microarray deductions through the use of nucleotides labelled with different beta-emitting radionuclides.

The invention discloses a combined treatment system and method for boron-containing radioactive waste liquid of a nuclear power plant. The system comprises a coarse filtration subsystem, a membrane separation subsystem and an ion exchange subsystem, wherein the coarse filtration subsystem is separately connected with the membrane separation subsystem and the ion exchange subsystem, the membrane separation subsystem is connected with the ion exchange subsystem, and the coarse filtration subsystem comprises a filtrator; the membrane separation subsystem comprises an ultrafiltration treatment device connected with an outlet of the filtrator and a multistage reverse-osmosis treatment device connected with the ultrafiltration treatment device, a dosing device is arranged between the ultrafiltration treatment device and the multistage reverse-osmosis treatment device, the multistage reverse-osmosis treatment device is connected with an auxiliary adsorption bed, and the auxiliary adsorption bed is connected with the filtrator of the coarse filtration subsystem; and the ion exchange subsystem comprises a plurality of ion exchange beds which are in series. According to the system and the method, radioactive nuclides and boron can be simultaneously removed from waste liquid of a primary circuit of a pressure water reactor, and the system and the method have a good treatment effect on the radioactive nuclides in different presence forms.

The invention provides a super heat resistant ceramic wok and a manufacturing method thereof. The ceramic wok adopts the main raw materials of spodumene, quartz, kaolin, talc and waste ceramic slag, and a high-performance polyacrylamide dispersing agent is also added, thereby the dispersity and the stability of ceramic slurry are improved. Meanwhile, a small amount of niobium oxide is doped so asto restrain material grain growth and reduce an expansion coefficient and ensure that a product has small cracking and deformation and excellent thermal shock resistance. The super heat resistant ceramic wok can be suitable for quick-fry and cannot crack with intense fire and dry burning. The super heat resistant ceramic wok can also resist heat exchange at 650-20 DEG C without cracking, be not easy to have wok sticking and cannot be oxidized or corroded without toxicity and harm. The lead and cadmium dissolution rate of the super heat resistant ceramic wok is zero, and a radio-nuclide limit also conforms to the national standard.

In an engineered barrier system for deep geological disposal of high level radioactive waste, a buffer backfill material is adopted as the most important encapsulation facility for preventing radionuclide from migration to a groundwater environment. The present invention relates to a measurement apparatus for swelling force change of a buffer backfill material along with water absorption change, and a measurement method thereof. According to the present invention, the periphery of a buffer backfill material sample is enclosed with a ring knife; upper water penetrating stone and lower water penetrating stone are respectively placed above the buffer backfill material sample and below the buffer backfill material sample; a recess is arranged on the middle position of the lower part of the upper water penetrating stone; a soil pressure sensor is arranged inside the recess; the buffer backfill material sample is clamped in a clamper with the upper water penetrating stone and the lower water penetrating stone; the clamper clamping the buffer backfill material sample is positioned in a closed container; the soil pressure sensor is communicated with a strain gage outside the closed container through a conducting wire; and a water loading volumetric cylinder having scale is arranged outside the closed container, and is communicated with the closed container through a duct.

The invention relates to a method for drying radioactive waste ion exchange resin using microwaves in a barrel. The method comprises the steps that (1) the radioactive waste ion exchange resin is drained; (2) the drained radioactive waste ion exchange resin is conveyed to the stainless steel barrel; (3) the radioactive waste ion exchange resin contained in the stainless steel barrel is subjected to drying treatment by utilizing the microwaves, and in addition, the temperature is monitored; (4) after the stainless steel barrel reaches the preset filling rate, the drying stops, and the sealed storage treatment is carried out. The invention also provides a drying device for realizing the method. The method and the drying device have the advantages that a microwave pressurized water evaporation technology is adopted, the drying process can be enabled to be fast and stably carried out, the heating uniformity and the invariance of the resin are ensured, and in addition, the shifting out of radioactive nuclides along with moisture boiling can be reduced to the greatest degree; the drying device can realize the continuous feeding and the automatic control, the drying process is carried out in the stainless steel barrel in a drying cabin, and the possibility of injury on personnel and pollution on equipment and environment caused by the radioactive nuclides can be reduced.

The present invention belongs to the field of preparation of radioactive nuclide. It discloses a kind of preparation method of radioactive iodine and the intermittent closed circuit apparatus that used in this method. The characteristic of this method is irradiated the Xe gas in the irradiation bottle that placed in the reactor active area and transferred it out of the reactor to disintegrate, separate, recycle, purify, split charging, etc. At the same time, the circulating irradiated Xe gas would be inflated to the irradiation bottle of reactor active area, and the process of irradiation and disintegration would be carried on. The characteristic of this apparatus is that except irradiation bottle is in the active area of reactor, all the other equipments are placed out of the noumenon of reactor and connected to the irradiation bottle through main pipe. And there are 2 to 7 used disintegration bottle. The needle-shape tube with the cooling trap is connected to the main pipe between the irradiation bottle and aspirator. íí

Improved in-situ remediation systems which can be used to reclaim contaminated soils impacted by salts, heavy metals, and radionuclides by provision of multiple methods and devices for the contaminated soil remediation including electrokinetic method and devices, leaching solution supply and removal methods and devices, soil negative pressure moisture control method and devices, pressurized leaching / extraction method and devices, and sequential leaching / extraction methods and chemicals for the improvement of the remediation efficiency, enhancement of contaminants migration rates, shortening of remediation period, and prevention of secondary subsurface contamination.

The invention relates to a particulate material having a diameter in the range of from 5 to 200 microns comprising polymeric matrix and stably incorporated radionuclide, processes for its production and a method of radiation therapy utilising the particulate material.

The invention relates to a RGD polypeptide radiopharmaceutical used for integrin alphavbeta3 positive tumor. The RGD polypeptide radiopharmaceutical comprises RGD polypeptide, difunctional Chelator and radioactive Nuclide. The RGD polypeptide is RGD cyclic peptide dimer which is RGD cyclic peptide dimer E(L-c(RGDxK))2 which is synthesized by connecting the coupling agent L with RGD polypeptide monomer c(RGDfK) and dimerizing two RGD polypeptide monomer L-c(RGDfK) which are connected with the coupling agent L. The radioactive nuclide marks the RGD cyclic peptide dimer by one difunctional Chelator, and pharmacokinetic modifying molecule PKM is connected between the RGD cyclic peptide dimer and the difunctional chelator. The RGD polypeptide radiopharmaceutical is Nuclide-Chelator-PKM-E(L-c(RGDxK))2, and the RGD polypeptide radiopharmaceutical is colorless transparent liquid injection.

The invention discloses a surface-modified biochar adsorption material. The biochar adsorption material is biochar of which the surface is modified with amino. The preparation method comprises the following steps: S10, providing a biomass material, and carrying out high-temperature anaerobic cracking treatment on the biomass material to prepare biochar; and S20, placing the biochar in a reaction cavity of low-temperature plasma, vacuumizing until the air pressure in the cavity is stable, introducing a reaction gas containing ammonia gas, and performing surface modification on the biochar through low-temperature plasma discharge to prepare the biochar with the modified amino on the surface. The biochar adsorption material provided by the invention is applied to treatment of water body pollution, and pollutants such as heavy metal ions and radionuclide ions in water bodies can be effectively adsorbed and removed.

The present invention relates to a process for the manufacture of a glass frit for the containment by vitrification of a material comprising at least one oxidizable or reducible chemical species, and also to a process for the containment of said material by vitrification. The process for the manufacture of the glass frit comprises a step of incorporating into a raw glass frit at least one redox couple, the nature and the amount of which make it possible to maintain said at least one chemical species in its oxidized or reduced state. The containment process comprises mixing and hot melting the resulting glass frit and the material to be contained. The present invention makes it possible to optimize the containment of pollutants such as radionucleides, metals and metalloids. The material may be nuclear waste or a material derived from the incineration of household refuse.

The apparatus for the determination of radionuclides in a continuous flow of a fluid comprises an alpha-beta chamber that converts alpha, beta and gamma radiation into photons; a gamma chamber that converts gamma radiation into photons; an external covering shield that isolates the alpha-beta chamber and the gamma chamber from environmental UV-visible light; and means for separatedly sending photons generated in the chambers to an analyzing unit. It permits determinations on-line, remotely, and continuously.

The present invention discloses a DBN based separation method of a mixture of dual-tracer single-acquisition PET signals labelled with the same isotope. It predicts the two separate PET signals by establishing a complex mapping relationship between the dynamic mixed concentration distribution of the same isotope-labeled dual-tracer pairs and the two single radiotracer concentration images. Based on the compartment models and the Monte Carlo simulation, the present invention selects three sets of the same radionuclide-labeled tracer pairs as the objects and simulates the entire PET process from injection to scanning to generate enough training sets and testing sets. When inputting the testing sets into the constructed universal deep belief network trained by the training sets, the prediction results show that the two individual PET signals can been reconstructed well, which verifies the effectiveness of using the deep belief network to separate the dual-tracer PET signals labelled with the same isotope.

The present invention relates to radionuclide complex solutions of high concentration and of high chemical stability, that allows their use as drug product for diagnostic and / or therapeutic purposes. The stability of the drug product is achieved by at least one stabilizer against radiolytic degradation. The use of two stabilizers introduced during the manufacturing process at different stages was found to be of particular advantage.

The present invention relates to radionuclide complex solutions of high concentration and of high chemical stability, that allows their use as drug product for diagnostic and / or therapeutic purposes. The stability of the drug product is achieved by at least one stabilizer against radiolytic degradation. The use of two stabilizers introduced during the manufacturing process at different stages was found to be of particular advantage.

The invention discloses a derivate for labeling bile acid shown in formula VI, wherein A is -(CH2CH2)x- or -(CH2CH2O)m(CH2CH2)n-, x=1-4, preferably 1 or 3, m=1-3, preferably 1, n=1, and R1,R2 and R3 are hydrogen, alpha-OH or beta-OH respectively. The invention also provides a reference compound, a preparation method and an application of the derivate for labeling bile acid. The invention utilizes radioactive nuclide 99mTc to indirectly label bile acid for the first time, and the derivate for labeling bile acid in the invention has good application prospect of raster display.

The invention relates-a borosilicate glass ceramic curing base material, and a preparation method and an application thereof. The borosilicate glass ceramic curing base material comprises, by mass, 47-65% of SiO2, 8-15% of B2O3, 10-15% of Na2O, 4-10% of CaO, 8-13% of TiO2, 4-6% of ZrO2, 0.5-10% of CeO2, 0-2.5% of CaF2, 0-2.5% of Cr2O3, 0-2.5% of P2O5 and 0-2.5% of Fe2O3. The borosilicate glass ceramic curing base material has a simple preparation process and can be widely applied to curing treatment of high-level nuclear wastes. The multi-component curing base material is adopted, and variousradionuclides can be cured at the same time by adjusting the composition and content of the curing base material and adjusting the melting process; and radioactive nuclide is confined in a crystal structure, so actinide elements in the high-level radioactive wastes can be effectively cured, and the chemical stability and the package capacity of nuclear wastes in a cured body are greatly improved.

The present invention relates to radionuclide complex solutions of high concentration and of high chemical stability, that allows their use as drug product for diagnostic and / or therapeutic purposes. The stability of the drug product is achieved by at least one stabilizer against radiolytic degradation. The use of two stabilizers introduced during the manufacturing process at different stages was found to be of particular advantage.

The present invention is a method for suppressing corrosion of carbon steel members composing a nuclear power plant. That is, the processing solution contains a chemical including iron (II) ions, an oxidizing agent for oxidizing at least one part of the iron (II) ions into iron (III) ion, and a pH adjustment agent for adjusting pH. The pH of the processing solution is adjusted in the range of 5.5 to 9.0 by the pH adjustment agent. The processing solution is introduced into a purifying system pipe having the carbon steel members. The iron (II) ions are adsorbed on an inner surface of the purifying system pipe, namely, a surface of the carbon steel members. The ferrite film is formed on the surface of the carbon steel members by oxidizing the absorbed iron (II) ions. Therefore, corrosion of the carbon steel members is suppressed by the ferrite film.

The invention discloses a radioactive wastewater adsorption filter. The operation of replacing a filter bag is rapid and convenient; a compressing assembly is automatically loosened only by opening a top cover; after the compressing assembly is taken away, the filter bag filled with a filter material is rapidly lifted out from the upper part and a new filter bag with the filter material is put in again; and then, the compressing assembly is put back, the top cover is closed and the new absorption can be started. The filter bag is rapidly replaced to reduce the radiation on personnel to a maximum extent. Aiming at special nuclides, the filter bag with a characteristic absorption material is chosen or replaced, so that the removal rate of radioactive nuclides can be effectively improved. In addition, in an adsorber, a coupling layer capable of being compressed surrounds and tightly covers the external side face of the filter bag, so that the radioactive wastewater flows through the filter bag from top to bottom after entering a drum body via a water inlet at the upper part, and flows out of drain meshes at the bottom of the filter bag and the bottom of a fixing frame; the outflow at the side face of the filter bag is avoided, that is, the short-circuit current is avoided; the radioactive wastewater sufficiently flows through the filter bag from top to bottom, so that the nuclides in the wastewater are completely adsorbed by the filter material in the filter bag and the nuclides in the wastewater are removed thoroughly.