332 results about "Radiogenic nuclide" patented technology

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 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 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 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 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.

The invention discloses a method for establishing a three-dimensional solving model of migration time of N16 nuclide on a secondary side of a steam generator. The method is suitable for three-dimensional calculation of radionuclide migration time and primary side coolant leakage amount in the process that coolant with N16 nuclide on the primary side leaks and migrates to a secondary side nuclide monitoring point under the working condition that a heat transfer pipe of a nuclear power system steam generator is damaged. The establishment of the numerical calculation model mainly comprises the following steps of: 1, performing geometric simplification of the steam generator and establishment of a three-dimensional geometric model; 2, dividing calculation nodes on two sides of the steam generator; 3, establishing a transient three-dimensional thermal hydraulic calculation model of the steam generator; 4, determining N16 nuclide concentration at leakage positions of a heat transfer tube anda leakage part; 5, carrying out N16 nuclide migration time tracking and N16 nuclide decay migration model development; and 6, iteratively calculating the migration time of the N16 nuclide from the leakage point to a nuclide monitoring position, deriving to obtain the leakage amount of a coolant according to the nuclide migration time and the specific activity, and predicting a rupture position through the crevasse leakage amount.

The invention provides a composite hydrogel, impermeable coiled material as well as preparation method and application of composite hydrogel, impermeable coiled material, and specifically relates to acomposite hydrogel impermeable coiled materials which can be used for a nuclear waste disposal isolation layer. The impermeable coiled material is composed of a surface protective layer, the composite hydrogel, and a bottom support layer, the composite hydrogel is located between the surface protective layer and bottom support layer, the preparation method comprises the following steps: pressingfiber-reinforced hydrogel prepared from fiber, hydrogel, filler, a modification agent, a coupling agent, a mildew preventive and water between the surface protective layer and the bottom support layer, obtaining a composite hydrogel impermeable coiled material product. The impermeable coiled material prepared by the invention mainly used for coating the isolation layer of a waste liquid tank in anuclear waste disposal repository, and an isolation layer laid between a buffer layer and surrounding rock, the erosion of buffer layer material under the long-term action of groundwater can be effectively prevented, and further the radioactive nuclide is solidified, the safety and long-term effectiveness of nuclear waste disposal repositories are improved.

The invention relates to a medical polymer material with a radioactive nuclide marker, and a preparation method as well as application thereof, and belongs to the technical field of medicine and pharmacology. The medical polymer material with the radioactive nuclide marker is structurally a 18F<->-SFB-medical polymer material. The preparation of the medical polymer material with the 18F-marker comprises the steps of: reacting 18F<-> with an SFB precursor to obtain 18F<->-FBA; then reacting 18F<->-FBA with TSTU to obtain 18F<->-SFB; finally reacting the medical polymer material with triethylamine and 18F<->-SFB, and then centrifuging and washing to obtain the medical polymer material with the 18F<->marker. According to the provided method, the marked medical polymer material is separated and purified through the adoption of a centrifugal crystallization way, and the centrifuged product is a solid. The preparation method of the medical polymer material with the radioactive nuclide marker avoids the problems of increased attenuation amount of radionuclide and organic solvent residue caused by fussy operation of a chromatography in the prior art efficiently, and the obtained product has higher purity which can be more than 95%.

The invention discloses a complex environment emission/release nuclide dose calculation method. The method comprises the steps of calculating nuclide concentrations at different distances in a downwind direction according to a nuclear facility release source item; calculating the nuclide concentration in the downwind direction of the smoke plume center line in the complex environment according tothe topographic characteristics of the nuclear facility site; calculating the emission height of the smoke plume in the complex environment of the nuclear facility when the atmospheric stability is neutral or unstable; calculating the radionuclide concentration in the downwind direction of the central line of the smoke plume released by the nuclear facility under the influence of surface roughness; calculating accident atmospheric dispersion factors of the nuclear facility complex environment in different time periods; and calculating the public personal effective dose and thyroid dose causedby radionuclide when the nuclear facility complex environment accident is released. The method has the advantages that the calculation method is scientific, reasonable and high in applicability, is animportant technical means for radionuclide environmental impact evaluation under complex environmental conditions, and has important significance in the technical field of radionuclide atmospheric environmental impact evaluation.

The invention discloses a radioactive waste liquid treating method, a radioactive waste liquid treating device and a facility. Radioactive waste liquid is treated by the two-stage cascade radioactive waste liquid treating device including a first reactor and a second reactor, the obtained radionuclide content in second radionuclide is small and meets the discharge standard. The energy consumption is low, the handling capacity is large, and the amount of produced radioactive solid waste is small.

The present invention relates to a radionuclide adsorbent, which includes a hollow space (specifically, an area which is entirely empty or in which transition metal oxide particles are present); and a transition metal-ferrocyanide shell (specifically, a transition metal-ferrocyanide shell having a structure in which a plurality of two-dimensional nano flakes overlap or a transition metal-ferrocyanide shell having a structure in which a plurality of three-dimensional nano polyhedrons agglomerate) formed on the space surface, a preparation method thereof, and a method of removing a radionuclide using the same.