62results about How to "Avoid radioactive contamination" patented technology

The invention belongs to the technical field of preparation of radioactive sources, and discloses an electric deposition device for preparing a high-resolution alpha source. The electric deposition device comprises a power supply, an electric plating tank, a bottom weigher, a magnet and a platinum electrode; the electric plating tank is of a two-layer structure with an inner layer and an outer layer; openings are formed in the upper end and the bottom of the inner layer; the inner layer of the electric plating tank is used for accommodating electric deposition plating liquid; a cooling circulating water inlet and a cooling circulating water outlet are formed in opposite angles of the outer layer; an upper sealing ring and an upper sealing cover on the upper side are arranged in the opening in the upper end of the inner layer; a lower sealing ring and a lower sealing cover on the lower side are arranged in the opening in the bottom of the inner layer; the bottom weigher serves as a cathode, and is tightly attached to the lower portion of a hole way in middle of the lower sealing ring; and the platinum electrode extends from the radial center position of the upper end of the inner layer of the electric plating tank to a position 0.5-1 cm away from the bottom of the electric plating tank. The alpha source prepared by the device has the beneficial effects of high electric deposition efficiency, a compact plating layer, good uniformity and low deposition thickness.

The invention provides a radioactive waste bin batch-conveying and measuring device comprising a waste bin measuring system, an upstream waste bin batch-conveying assembly, a downstream waste bin batch-conveying assembly, and waste bin conveying plate trailers. The waste bin measuring system is arranged between the upstream waste bin batch-conveying assembly and the downstream waste bin batch-conveying assembly. Both the upstream waste bin batch-conveying assembly and the downstream waste bin batch-conveying assembly are equipped with a plurality of waste bin conveying plate trailers arranged in sequence. The waste bin conveying plate trailers are used for bearing radioactive waste bins to be conveyed. According to the invention, as the waste bin conveying plate trailers are arranged, direct contact between the upstream waste bin batch-conveying assembly and the downstream waste bin batch-conveying assembly is avoided, and radioactive contamination is prevented. The waste bin conveying plate trailers and waste bins are in static contact and are isolated by special isolation paper which is easy to handle after radioactively contaminated.

The invention provides a system for conducting combined supply of steam, thermal and electricity by utilizing nuclear energy. The system for conducting combined supply of the steam, the thermal and the electricity by utilizing the nuclear energy comprises a steam generator secondary side loop, a heat supplying loop and an industrial steam supplying loop. A part of main steam generated by a steam generator is used for generating electricity, another part of the main steam or inlet steam of a low pressure cylinder of a steam turbine is led into the heat supplying loop, and the rest part of the main steam or extracted steam of a high pressure cylinder of the steam turbine is led into the industrial steam supplying loop; and a heating steam condensing water cooler is arranged in the steam generator secondary side loop, steam condensed water flows of the heat supplying loop and the industrial steam supplying loop are discharged into a steam condenser after passing through the heating steam condensing water cooler, and condensate water of the steam condenser passes through the equipment of a condensate polishing treatment device, the heating steam condensing water cooler and the like and returns back to the steam generator. According to the system for conducting combined supply of the steam, the thermal and the electricity by utilizing the nuclear energy, the multi-function of conducting combined supply of the steam, the thermal and the electricity by utilizing the nuclear energy is achieved, the thermal efficiency and the applicability of a nuclear power station are improved, and the safety of steam supplying and heat supplying by utilizing the nuclear energy is improved by adopting various technological methods.

The invention provides a stoneware sheet and a preparation method thereof. The stoneware sheet comprises the following chemical components in percentage by weight: 55-68% of SiO2, 14-28% of Al2O3, 0.5-1.8% of Fe2O3, 0.2-1.5% of TiO2, 1-12% of CaO, 0.3-1% of MgO, 2-5% of K2O and Na2O and 5-30% of fiber reinforcer. The preparation method comprises the following steps: independently ball-milling and pulping the fiber reinforcer, mixing with other pulping raw materials, carrying out spray granulation, and dry-pressing to obtain the green body. The stoneware sheet has the advantages of favorable adhesiveness, high strength, favorable flatness, high resilience and flexibility, high abrasive resistance, favorable anti-fouling performance, fire resistance, high temperature resistance, long service life, no radioactive contamination, light weight and the like.

The invention relates to a microwave-assisted low-temperature acid pickling method of rare-earth ore concentrate, and belongs to the technical field of mineral extraction and metallurgy. The microwave-assisted low-temperature acid pickling method comprises the following steps: (1) uniformly mixing the rare-earth ore concentrate with concentrated sulfuric acid based on a certain ratio; (2) heating for 3 to 15 minutes through a microwave chemical reacting furnace at 90 to 200 DEG C, and fully dissolving the rare-earth ore concentrate; and (3) separating rare-earth leaching liquid from leaching residue in a centrifugal water washing way, so as to complete the leaching of the rare earth. According to the microwave-assisted low-temperature acid pickling method of rare-earth ore concentrate, the microwave-assisted and low-temperature acid pickling way is carried out on the rare earth, so that the leaching time is short, the rare-earth leaching rate is high, little consumption is brought to acid agent, the energy consumption is low, the emission of thorium and harmful gas is reduced, the recycle of the thorium is realized, the production efficiency is improved, and the pollution to environment is reduced as well; and the microwave-assisted low-temperature acid pickling method of rare-earth ore concentrate is an economic and environment-friendly method, and brings actual guiding significance to the rare-earth smelting process.

The invention discloses a multilayer composite neutron target which comprises a surface tritium barrier permeable layer, a tritium storage layer, an internal tritium barrier permeable layer, a hydrogen isotope storage layer, a buffer guiding layer and a base layer in order. The tritium storage layer is a core part of a neutron target and is mainly used for storing tritium, the effect of the surface tritium barrier permeable layer is to prevent the tritium in the tritium storage layer from diffusing to the base layer. According to the invention, a multilayer design is used, the tritium escape in the tritium storage layer is effectively reduced, the yield and service life of the neutron target are improved, and at the same time, the radioactive pollution caused by the escape of tritium is reduced.

The invention utilizes the mud to calcine the bone ash case, relating to the funeral appliance technique field of bone ash case. The steps comprises that using the clear mud of Yellow River as raw material; selecting the mud material whose sand percent is 3-8 %; adding water to be dipped; continuous mixing straight forward; filtering four times at sequence; depositing and pumping water; airing and draining; kneading; removing gas holes; loading mould; unloading mould; dry in shade; finishing blank; carving the patterns of twelve Chinese zodiac; cleaning the opposite opens; sanding; burnishing in water; calcining in furnace for five days in the temperature that progressively increased from 800-1000 Deg. C; closing the furnace; opening the furnace and cooling; getting out from the furnace to be wax finished for the finished product of bone ash case made from mud. The invention can apply storage of bone ash, and has the advantages that utilizing the waste of mud of Yellow River, saving the natural resource of wood, fire prevention, and insect prevention.

The invention relates to a method for detecting 3'-5' exo-activity of DNA polymerase or mismatching and a kit thereof. The method comprises the following steps: providing a nucleic acid of a known sequence, detecting a primer which is complementary to a nucleic acid with the known sequence, wherein the last deoxynucleotide at the 3' hydroxyl end and the first two deoxynucleotides to-be-polymerizedare different from each other; hybridizing the nucleic acid with the known sequence and a detection primer, and adding the DNA polymerase to be tested and the fluorescently labeled deoxynucleotide different from the deoxynucleotide to-be-polymerized for the first signal collection; adding exo-free Taq DNA polymerase and adding the first fluorescently labeled deoxynucleotide to-be-polymerized andthe second fluorescently labeled deoxynucleotide to-be-polymerized, and performing secondary signal collection; comprehensively analyzing a first signal and a second signal to determine whether the DNA polymerase to-be-tested is circumscribed or mismatched. The method can detect DNA polymerase 3'-5' exo-activity or mismatching when four nucleotides are present alone in a reaction system.

A nuclear reactor is positioned on a barge which floats on the water of a water tank. The water tank includes a bottom wall, first and second end walls and first and second side walls. The bottom wall includes a lower layer of concrete, an intermediate layer of water impervious material positioned on the lower layer of concrete, and an upper layer of concrete positioned on the intermediate layer of water impervious material. Each of the first and second end walls and the first and second side walls includes an outer layer of concrete, an intermediate layer of water impervious material positioned at the inner side of the outer layer of concrete, and an inner layer of concrete material positioned at the inner side of the intermediate layer of water impervious material.

The invention discloses treatment equipment for radioactive element-containing polluted wastewater. The treatment equipment structurally comprises a treatment box, a water inlet connector, a first water pump, a second water pump, a stirring motor, a medicament inlet pipe and a water outlet connector. The treatment equipment has the following beneficial effects that cover opening and source closing devices are arranged at top covers of a sand filter tank and an activated carbon filter tank, the device is provided with a baffle which is jacked by a compression spring to automatically close a water inlet, the baffle is opened through an electromagnet, and an electromagnet switch is closed, jacked and opened through the top cover, so that the device can avoid wastewater input from the water inlet when the top cover is not opened, and radiation pollution caused by the fact that the top cover is not closed is avoided; the cover locking devices are arranged in the sand filter tank and the activated carbon filter tank, each cover locking device is composed of a manually-controlled control rod and a cover locking plate which are matched with a floating rod for internal locking and a clamping groove, and when sewage exists in the sand filter tank and the activated carbon filter tank, the sewage can jack and press the floating rods to enter the clamping grooves, so that the cover locking plates are internally locked, and the radioactive pollution danger caused by mistaken opening is better avoided.

The invention discloses a kit for measuring an rT3 content by a magnetism particulate chemiluminescence method and a detection method of the kit. The kit provides a preparation method of an rT3 antigenic derivative, the rT3 antigenic derivative and an enzyme-labeled rT3 antigenic derivative are prepared, and a biotinylated rT3 antigenic derivative, anti-body enzyme-labeled reagent and calibrationproduct detection system and an enzyme-labeled rT3 antigenic derivative, biotinylated rT3 rabbit polyclonal and calibration product detection system can be built. As an enzymatic luminescence system possibly needs to perform coupling under different conditions such as biotin, enzyme labels and even protein on rT3 antigens under different conditions, the rT3 antigenic derivative serving as an intermediate is prepared, and the problem can be solved. Detection value and given value correlations of different systems are 0.9 or more, good correlations are shown, the correlations of two measuring systems are 0.9540, good correlations of two testing methods are shown, and testing results are consistent, a whole reaction system is short in reaction time, radioactive pollution is avoided, a validity period of a reagent is prolonged, the kit is high in sensitivity and accurate in testing result, and test operation processes are simplified.

The invention discloses a method for detecting 3'-5' exo-activity of a specific base by nuclease and a kit thereof. The method firstly detects the exo-activity of the specific base by enzyme; the method can detect any base, including dATP, dCTP, dGTP, dTTP, dUTP and degenerate base, and the like, and the application range is wide; the method can detect the 3'-5' exo-activity of most nucleases; theuse of fluorescence as a detection signal avoids radioactive contamination and has high sensitivity; nucleotide chains modified by fluorophores cannot be required, and the cost is low; the method canbe used to rapidly and extensively screen nucleases, and the application is flexible and the flux is high.

The invention discloses a radioisotope logging tracer underground screening method. The method comprises the following steps that a mixed tracer is added into an isotope bin of a screening device; the valve is opened, and the isotope tracer agent is soaked in the injected water; the valve is closed, and the injected water in the isotope bin is in a static state; in the static state, the tracers in the isotope bin are layered, the tracers with the same specific gravity as the injected water are suspended, and the isotope logging tracers with the specific gravity closest to the specific gravity of the injected water of the to-be-logged section can be screened out; the tracer most matched with the specific gravity of the injected water can be screened out, the problem that isotope logging data are unqualified due to the fact that the specific gravity of the tracer is not matched is solved, and the method is particularly significant to water injection and fine logging of different logging blocks and different mineralization degrees of an oil field. The breakage rate and the isotope desorption rate of the tracer agent are detected by replacing an expensive and huge ultrahigh pressure generating device during ground detection with the high pressure and the real temperature environment of underground injected water, and the problems of radioactive contamination and data distortion are solved.

The invention discloses an angiotensin II magnetic particle chemiluminescence detection kit, which comprises a streptavidin magnetic particle magnetic separation reagent, a biotinylated angiotensin IImonoclonal antibody, an alkaline phosphatase-labeled angiotensin II derivative and a calibrator. The kit has the advantages of high sensitivity, selectivity and specificity. The invention also discloses a detection method of the angiotensin II magnetic particle chemiluminescence detection kit, and the method is simple, avoids radioactive contamination and prolongs the expiration date of the reagent.

The invention relates to an on-line visual pack absence detection device and a detection method for a cigarette pack cartoning machine. A visual unit collects images during the cigarette pack cartoning process, and is connected with a data management system via an Ethernet switch for data communication. A barcode scanner and a control module collect cigarette carton barcode information and transmit the cigarette carton barcode information to the data management system. An input and output control module receives rejecting signals of the visual unit, and outputs the rejecting signals to a warning and rejecting module. The method comprises the steps of initializing the detection device; judging whether a cigarette pack of a certain layer in the cartoning machine is in place; if in place, processing, analyzing and transmitting images of the cigarette pack of the layer to the data management system; judging whether the cigarette pack of the layer has any defect; if so, emitting warming and rejecting signals. The invention prevents the radioactive pollution caused by radioactive substances in the measurement process and the contact pollution caused by artificial weighing measurement, reduces the system complexity, and avoids huge industrial control computer chassis or huge system control cabinets.

The invention discloses a radioisotope logging tracer underground screening device which comprises a device body, an upper isotope bin, a middle isotope bin and a lower isotope bin. The upper isotope bin, the middle isotope bin and the lower isotope bin are arranged in the device body. The upper isotope bin, the middle isotope bin and the lower isotope bin are sequentially arranged from top to bottom in the vertical direction, that is, the middle isotope bin is located between the upper isotope bin and the lower isotope bin, and the upper isotope bin is located at the upper part of the middle isotope bin; the tracer most matched with the specific gravity of the injected water can be screened out, the problem that isotope logging data are unqualified due to the fact that the specific gravity of the tracer is not matched is solved, and the method is particularly significant to water injection and fine logging of different logging blocks and different mineralization degrees of an oil field. The breakage rate and the isotope desorption rate of the tracer agent are detected by replacing an expensive and huge ultrahigh pressure generating device during ground detection with the high pressure and the real temperature environment of underground injected water, and the problems of radioactive isotope contamination and data distortion are solved.

The present invention disclosed a detection method of swine metallothionein, relates to detection method of animal metallothionein, it relates to a qualitative and quantitative detection method of swine metallothionein. Said invention uses electrophoretic pure mouse anti-swine metallothionein IgG as first antibody and uses goat anti-mouse enzyme-linked antibody as second antibody, and adopts solid-phase antigen indirect competitive type enzyme-linked immunosorbent assay method to determine the content of swine metallothionein. Said invention also provides the concrete steps of said method.

The invention relates to an applicator for applying a radioactive substance to a biological tissue, wherein the applicator comprises a container for receiving the radioactive substance, an application device with which the substance compound can be applied to the tissue and which can be connected to the container, and at least a part of a delivery device, by means of which the radioactive substance can be fed from the container into the application device when the application device is connected to the container.

The invention discloses a spent fuel post-treatment plant sample analysis method. The method comprises the following steps: establishing sample analysis tasks for a sample according to sample analysis requirements, wherein the sample analysis tasks comprise an automatic analysis task and a non-automatic analysis task; and firstly completing the automatic analysis task of a sample, and then completing the non-automatic analysis task of the sample. The invention also discloses a spent fuel post-treatment plant sample analysis system. The system comprises a transceiving unit, automatic analysis equipment and a non-automatic analysis unit; the transceiving unit is used for receiving the sample and distributing the sample according to a sample analysis task; the automatic analysis equipment is used for receiving the samples distributed by the transceiving unit and automatically analyzing the samples so as to complete an automatic analysis task of the samples; and the non-automatic analysis unit is used for receiving the sample distributed by the transceiving unit and carrying out non-automatic analysis on the sample so as to complete a non-automatic analysis task of the sample. The method and the system solve the problems of low analysis efficiency, low sample utilization rate, poor safety and the like.

A device for purification of water sink is provided to remove radioactive substances in a water sink of nuclear facilities. The device for purification of water sink of the present invention relates to a detachable structure for repeating process, changing the height of the device according to the water level, and moving the device. The device is filled with filter agent or adsorbent in each basket assemblies and put into a water sink for purification process. After purification process of water sink, the highly contaminated waste filter agent or waste adsorbent within the basket assemblies is easy to be removed from the device for drying. The number of basket assemblies is able to be reduced in accordance with the water level drop for draining fluid from the water sink at lower level water.

A device for purification of water sink is provided to remove radioactive substances in a water sink of nuclear facilities. The device for purification of water sink of the present invention relates to a detachable structure for repeating process, changing the height of the device according to the water level, and moving the device. The device is filled with filter agent or adsorbent in each basket assemblies and put into a water sink for purification process. After purification process of water sink, the highly contaminated waste filter agent or waste adsorbent within the basket assemblies is easy to be removed from the device for drying. The number of basket assemblies is able to be reduced in accordance with the water level drop for draining fluid from the water sink at lower level water.

The invention belongs to the technical field of target member preparation and discloses a uranium foil target member of low enriched uranium for irradiation production fission <99>Mo. The target member is of a sandwich-type structure and comprises an inner target cylinder, an outer target cylinder and uranium foil. The uranium foil is positioned between the inner target cylinder and the outer target cylinder. The internal diameter of the inner target cylinder is unchanged, the outer wall of the inner target cylinder is designed into a tapered structure with the conicity of 1:160. The uranium foil wraps the outer side of the inner target cylinder. The thickness of the uranium foil is 120-150[mu]m, the inner and outer surfaces of the uranium foil are plated with a fission recoil protection layer respectively, and the thickness of the protection layer is 12-18[mu]m. The outer diameter of the outer target cylinder is unchanged, the inner wall of the outer target cylinder is designed into a tapered structure, and the inner diameter and the inner wall conicity of the outer target cylinder are matched with the outer diameter and the outer wall conicity of the inner target cylinder respectively. The uranium foil target member has the beneficial effects that the target unbinding and melting is simple, the radiation efficiency is high and the radioactivity pollution can be reduced.

The invention provides a sealed carrier vehicle. The sealed carrier vehicle comprises a vehicle body, a roller device, a partition plate and two vehicle doors arranged left and right, the vehicle body of which the front is open is a cube, the edge of an opening of the vehicle body is fixedly provided with a sealing strip, the right vehicle door is pressed on the left vehicle door, and the sealing strip is fixedly arranged on the contact part of the right vehicle door and the left vehicle door; a rotating rod is arranged on the right vehicle door in a hinged mode, a handle is fixedly connected to the rotating rod, and the upper side and the lower side of the vehicle body are fixedly provided with locking devices, and the two ends of the rotating rod are fixedly provided with supporting devices matched with the locking devices; the vehicle body and the vehicle doors are all manufactured with an anti-radiation material; circular holes are formed in the vehicle doors, and the circular holes are fixedly connected with anti-radiation gloves; square holes are formed in the back side wall of the vehicle body, an anti-radiation sealing baffle is arranged in the square holes, the partition plate is an operation platform connected inside the vehicle body in a sliding mode, through holes are formed in the operation platform, and an anti-radiation baffle is arranged in the through holes; the lower portion of the operation platform is provided with an anti-radiation recycle frame, through holes are formed in the position of the top of a frame body, corresponding to the through holes, and a closing plate is arranged at the position of the through holes.

The invention provides a waste bin segmental gamma scanning device, which includes a detection device, a lead shielding body, a supporting platform, a rotating device, a driving device, a lifting device and a waste bin, and the supporting platform includes an upper platform and a lower base; the upper platform is installed There is a lead shielding body and a detection device, and the detection device detects the waste bin entering the lead shielding body; a lifting device is arranged between the upper platform and the lower base, and the lifting device can drive the waste bin to move up and down between the lower base and the lead shielding body; The base is provided with a driving device, which can drive the rotating device to reciprocate between the lower base and the lifting device; the rotating device can drive the waste bucket to rotate. The invention eliminates the influence of the environmental background on the measurement results of low-level radionuclides in the waste barrel, solves the problem that the current SGS device with a shielded lead chamber cannot detect the entire waste barrel, saves materials and reduces costs. The problem of radioactive contamination in the lead chamber is avoided.

The invention discloses a method for rapid detection and screening of DNA polymerases capable of polymerizing dNTPs with special structures. The present invention provides a method for detecting whether a DNA polymerase to be tested can polymerize dNTPs of a specific structure, comprising the following steps: 1) preparing a single-stranded DNA molecule and a hybrid single-strand complementary to it; In the 3' direction, the adjacent base B and base A are arranged in sequence; 2) The single-stranded DNA molecule, the hybrid single-stranded, the specific structure dNTP and the DNA polymerase to be tested are placed in the system DNA polymerization reaction was carried out in the test to check whether the polymerization was successful. The detection method of the invention has the following advantages: wide application range, no pollution, feasibility, flexible flux, and high flux.

The invention is a kit for measuring digoxin content by magnetic particle chemiluminescence method and a detection method thereof, and provides a preparation method of digoxin antigen derivatives, which can realize the indirect linking of digoxin antigens with biotin or enzymes, Two detection systems of biotinylated digoxin antigen derivative + antibody enzyme-labeled reagent + calibrator and enzyme-labeled digoxin antigen derivative + biotinylated digoxin mouse monoclonal antibody + calibrator were constructed in the kit. It can be used for solid-phase coupling and luminescence-labeled digoxin derivatives. It is suitable for coupling digoxin antigens in different situations such as biotin, enzyme labels and even proteins, so that different companies can be more accurate when testing. Flexible selection, and can be realized only by preparing the intermediate of digoxin antigen derivative. The correlation between the measured value and the given value of different detection systems established by using this derivative is above 0.96, and the correlation between the two detection systems is 0.9585. The reaction time of the whole reaction system is short, radioactive pollution is avoided, the validity period of the reagent is extended, the sensitivity is high, the test result is accurate, and the experimental operation process is simplified.

Methods and kits for rapid detection of DNA polymerase 3'‑5' exonuclease activity or mismatches. The method includes: providing a nucleic acid of known sequence, and detection primers, which are complementary to the nucleic acid of known sequence, and the last deoxynucleotide at the 3' hydroxyl end and the first two deoxynucleotides to be polymerized are different from each other ;Hybridize the nucleic acid of known sequence and the detection primer, add the DNA polymerase to be tested and the deoxynucleotide with fluorescent label, which is different from the deoxynucleotide to be polymerized, for the first signal collection; Taq DNA polymerase, and add the first deoxynucleotide to be polymerized with fluorescent label and the second deoxynucleotide to be polymerized with fluorescent label, and carry out the second signal collection; comprehensive analysis first The secondary signal and the second signal are used to determine whether the DNA polymerase to be tested undergoes excision or mismatch. It can detect DNA polymerase 3'‑5' exoactivity or mismatch when four nucleotides exist alone in the reaction system.

The invention discloses a method and a kit for detecting the 3'-5' excision activity of a nuclease on a specific base. The present invention proposes for the first time to detect the exolytic activity of an enzyme to a specific base; any base can be detected by using the invention, including dATP, dCTP, dGTP, dTTP, dUTP and degenerate bases, etc., and the application range is very wide; the invention can Detects the 3'-5' exoactivity of most nucleases; uses fluorescence as the detection signal, avoids radioactive contamination, and has high sensitivity; does not require fluorophore-modified nucleotide chains, and has low cost; can be used for rapid and large-scale Screen nucleases with flexible applications and high throughput.

The invention relates to the technical field of pressurized water reactor nuclear power plants and discloses a recycling method for radioactively-contaminated scrap iron and steel generated by a pressurized water reactor nuclear power plant. The recycling method comprises the following steps: transporting the radioactively-contaminated scrap iron and steel generated by the pressurized water reactor nuclear power plant to a smelting plant for smelting and decontaminating, and casting molten steel obtained by smelting the radioactively-contaminated scrap iron and steel to form a shielding container; using the shielding container for fixed treatment of a radioactively-contaminated high-dose-rate filter element of a waste water filter for shielding the radioactively-contaminated high-dose-rate filter element of a waste water filter. According to the method provided by the invention, the radioactively-contaminated scrap iron and steel can be recycled for manufacturing the shielding container; the shielding container is used for the subsequent fixed treatment of the radioactively-contaminated high-dose-rate filter element of a waste water filter, replaces heavy metal lead and can be used for shielding the radioactively-contaminated high-dose-rate filter element of a waste water filter, so that radioactive contamination of the filter element to the environment is avoided, better environment friendliness is realized, and the cost is reduced.