122results about How to "Improve radiation effect" patented technology

Impurity is removed from gas, the resultant gas is introduced into a cell 15, and the intensity of light transmitted through the cell 15 is measured as a reference. Gas containing impurity of which concentration is known, is introduced into the cell 15, and the intensity of light transmitted through the cell 15 is measured with the temperature and pressure maintained at those used at the measurement of the reference light intensity. Then, the absorbance of the impurity is obtained according to the ratio of the two light intensity data obtained by the two measurements above-mentioned. The impurity absorbance thus obtained is stored, in a memory 20a, as a function of an impurity concentration. Gas containing impurity of which concentration is unknown, is introduced into the cell 15, and the intensity of light transmitted through the cell 15 is measured with the temperature and pressure maintained at those used at the measurements above-mentioned. The absorbance of the impurity is obtained according to the last-measured light intensity and the reference light intensity. The absorbance thus obtained is applied to the function, thereby to obtain the impurity concentration.

The invention belongs to the technical field of nuclear reactor design, and in particular relates to a reactor core with high fast neutron fluence. The reactor core consists of fuel assemblies, control rod assemblies and beryllium assemblies. The plurality of fuel assemblies are hexagonal sleeve type fuel assemblies and in annular compact arrangement; six fuel assemblies are arranged on an innermost ring to form a fast neutron trap at the center of the annular region; the plurality of hexagonal beryllium assemblies are arranged close to the external side of the annular region of the fuel assemblies to form an inverted neutron trap; and the plurality of control rod assemblies are arranged among the fuel assemblies at intervals and in two rows and two columns in a squared shape. The reactor core with high fast neutron fluence satisfies internationally restricted U-235 enrichment degree and requirements of domestic fuel core production and design of coolant flow velocity, and can obtain high fast neutron fluence level in an irradiation tunnel, and enhance and widen irradiation capability and scope of application of a test reactor.

A building thermal insulation dry powder mortar belongs to a building thermal insulation material. The weight ratio of a dry powder to water is 1: 1.5. The dry powder is prepared by mixing 450 parts by mass of ordinary portland cement, 70 parts by mass of a calcined gypsum powder, 37.5 parts by mass of a redispersible emulsion powder, 15 parts by mass of fine xylem fibers, 13 parts by mass of polypropylene staple fibers, 10 parts by mass of slaked lime, 10 parts by mass of sierozem, 10 parts by mass of heavy calcium carbonate, 3 parts by mass of hydroxypropyl methyl cellulose, 364 parts by mass of a calcined expanded perlite and 17.5 parts by mass of a premixed auxiliary agent. The thermal insulation building dry powder mortar has the advantages of strong thermal insulation, strong bond with walls, high compressive strength, strong drawing force, excellent weather resistance, and environmental protection, and also has the advantages of fire resistance, cracking resistance, leakage resistance, moisture resistance, sliding resistance, earthquake resistance and the like.

There is provided a method of forming a nitride semiconductor layer, including the steps of firstly providing a substrate on which a patterned epitaxy layer with a pier structure is formed. A protective layer is then formed on the patterned epitaxy layer, exposing a top surface of the pier structure. Next, a nitride semiconductor layer is formed over the patterned epitaxy layer connected to the nitride semiconductor layer through the pier structure, wherein the nitride semiconductor layer, the pier structure, and the patterned epitaxy layer together form a space exposing a bottom surface of the nitride semiconductor layer. Thereafter, a weakening process is performed to remove a portion of the bottom surface of the nitride semiconductor layer and to weaken a connection point between the top surface of the pier structure and the nitride semiconductor layer. Finally, the substrate is separated from the nitride semiconductor layer through the connection point.

The invention disclose a total absorption superlaser energy meter which comprises a reflection cone and an absorption cavity, wherein the generatrix of the reflection cone is arc-shaped, the absorption cavity is formed by sealed connection of a base plate, an inner lateral plate, an absorption cylinder and a cover plate, the whole structure of the absorption cavity is concave, the wall of the absorption cylinder is arranged on the light path of a superlaser beam after the superlaser beam is reflected through the reflection cone, and the absorption cylinder is located behind the reflection cone in the front and back direction. According to the total absorption superlaser energy meter, the incident collimated light beam is reflected onto the wall of the absorption cylinder in an axial and circumferential two-dimensional beam expansion mode, the power density of laser irradiating on the wall of the absorption cylinder is reduced greatly, the light receiving area of the reflection cone is increased at the same time, and the laser irradiation bearing capacity of the reflection cone is improved; furthermore, due to the adoption of the cavity structure, the probability that the reflection cone is polluted by dust is effectively reduced, and meanwhile, the exit escape rate of laser is reduced and measurement accuracy of the energy meter is improved.

The invention relates to a solar cell irradiation annealing furnace capable of uniformly and efficiently annealing. The solar cell irradiation annealing furnace comprises a furnace body, wherein the furnace body comprises an upper furnace body and a lower furnace body, at least one group of light sources are arranged in the upper furnace body, an air inlet is arranged between two adjacent groups of light sources or between the light sources and an upper furnace body framework, a diversion plate is arranged below the corresponding air inlet, a battery piece transmission device is arranged in the lower furnace body, a battery piece is horizontally transmitted in the battery piece transmission device and receives irradiation of the light sources, an air outlet is arranged in the lower furnace body below the battery piece and is externally connected with an air suction device, a temperature sensor is arranged in the furnace body, and the light sources, the battery piece transmission device, the air suction device and the temperature sensor are connected with a controller. The solar cell irradiation annealing furnace is simple in structure and reasonable in design, the processing temperature of the battery piece can be uniformly controlled, the problem of a non-uniform irradiation processing effect is solved, the irradiation annealing processing can be completed within 30 seconds, moreover, an LID is controlled within 1%, the processing time is shortened, and the annealing effect and the production efficiency are improved.

The invention discloses a low-zirconium white glaze for a sanitary ceramic. The low-zirconium white glaze comprises the following raw materials in percentage by mass: 6.5-7.5% of zirconium silicate, 24-27% of quartz, 5-7% of kaolin, 2.5-3.5% of aluminum oxide, 12-18% of potassium feldspar, 9-15% of albite, 6-8.5% of calcite, 9-13% of wollastonite, 2-5% of dolomite, 2-3.5% of sintered talc, 2-3.5%of zinc oxide and 1.5-4% of frit. The low-zirconium white glaze is prepared by using a preparation process through operation of steps (1)-(3). Under a condition of a low zirconium silicate content, high glossiness, high ceramic whiteness, good high-temperature flowability and low radioactivity of the low-zirconium white glaze can be still maintained, and the low-zirconium white glaze has the effects of high glossiness, high ceramic whiteness, good high-temperature flowability and low radioactivity.

The invention relates to a V-shaped reactor external melt retention device used after a nuclear power plant accident. The V-shaped reactor external melt retention device comprises an inner wall, a steam channel wall fixed at an opening in the bottom of the inner side of the inner wall, a pressure container arranged in the steam channel wall, an outer wall surrounding the inner wall, a reactor core melt retention device fixed at the bottom of the inner wall and a reactor core melt cooling device which is in tight contact with the bottom of the reactor core melt retention device, wherein a coolant descending channel is formed between the inner wall and the outer wall; a coolant channel is formed between the inner wall and the reactor core melt retention device; a reactor core melt retention groove is formed in the upper surface of the reactor core melt retention device under the pressure container; the lower surface of the reactor core melt retention device is a plane; the reactor core melt retention device is made of an inorganic non-metal fireproof material. By adopting a melt retention design outside a reactor, melts are accommodated by different materials and are cooled by a coolant loop and the reactor core melt cooling device, and therefore, the safety of a nuclear power plant.

The invention provides a soil heavy mental absorbing agent. The soil heavy mental absorbing agent comprises, by weight, 12-15 parts of peats, 2-6 parts of natural humus, 13-17 parts of lignin, 1-3 parts of chitin, 1-5 parts of zeolite, 3-8 parts of tetrabutyl titanate, 5-12 parts of silica solution, 6-8 parts of calcium aluminate, 3-7 parts of volcanic, 6-9 parts of polyamide 6 (PA6) powder, 1-3 parts of gelatin, 2-4 parts of ammonium hydrogen carbonate and 3-45 parts of inorganic minerals. Compared with the prior art, the soil heavy mental absorbing agent has the advantages that the soil heavy mental absorbing agent is low in cost, convenient in raw material obtaining and suitable for being popularized and applied widely in development of green and pollution-free agricultural product industries; due to high chitin molecular weight, the soil heavy mental absorbing agent is strong in absorbing ability and suitable for being applied in the manufacturing industry and the environmental protection field; in addition, the chitin has a natural anti-bacteria effect, so that the soil heavy mental absorbing agent is high in broad-spectrum antibacterial rate.

The invention provides an antenna filtering circuit in an electronic terminal, an antenna filtering method and an electronic terminal. A metal frame of the electronic terminal is divided into at leasttwo parts through at least one slit. Each of the at least two parts is made into an independent antenna, so that at least two antennas are formed. Any one of the at least two antennas is determined as a target antenna. The antenna filtering circuit includes a multi-channel changeover switch and a plurality of filters, wherein a first connection end of the multi-channel changeover switch is connected to a first predetermined position of an antenna adjacent to the target antenna, a second connection end of the multi-channel changeover switch can be connected to first ends of the different filters, and a second end of each filter is grounded. By adopting the antenna filter circuit in an electronic terminal, the antenna filtering method and the electronic terminal in the exemplary embodimentof the invention, the isolation degree between adjacent antennas can be increased, the mutual coupling effect between adjacent antennas can be reduced, and the overall radiation performance of antennas can be improved.

Disclosed in the present invention is a contrast constrained aerothermal radiation correction method. By analyzing features of images at different intensities of aerothermal radiation, it has been discovered that the stronger the aerothermal radiation effect is, the smaller the image contrast becomes, and when thermal radiation correction is performed using a gradient fitting algorithm, it has been discovered that time consumption thereof grows exponentially with an increase in a degree of a fitting surface and with an increase in an image size. The present invention can rapidly and effectively restore an aerothermal radiation image, remarkably improving a signal to noise ratio and quality of the image.

The invention belongs to the field of the preparation of stress corrosion tensile samples, and particularly relates to a stress corrosion tensile sample adopting ion irradiation to simulate neutron irradiation and a preparation method, which is used for studying stress corrosion sensitivity of an irradiated material so as to evaluate the service performance of the material in a high-temperature high-pressure water environment of a nuclear power plant. The tensile sample comprises parallel portion scale distance section with a rectangular cross section, a tangential transitional arc portion and a threaded connection clamping portion. The preparation method comprises the following steps: (a) preparing a sample unit body; (b) grinding by using abrasive paper; (c) manually polishing; (d) ultrasonically cleaning; (e) pre-observing; and (f) performing EBSD detection. The stress corrosion tensile sample provided by the invention can uniformly receive the ion irradiation, and can effectively enable the influence of the irradiation to be prominent; the preparation method is simple, the practicability is high, and the cost is low; and the preparation method can effectively avoid the change of chemical components on the surface of the sample.

The invention belongs to the biological engineering field and discloses a recombinant octreotide and an application thereof. Aiming at the problems that the prior octreotide can not realize targeting short-distance irradiation towards tumour cells and can not be applied to the preparation of targeting curative drug, the invention provides a recombinant octreotide, the amino acid sequence of which is shown as SEQ ID NO.2. The recombinant octreotide is in favor of radioactive isotope <131>I marking and can be applied to the preparations of antitumor drug or targeting diagnosis reagent.

The invention relates to an active hydrogen generator which is provided with a supercharging device, a water activating device, a hydrogen enriching device and an electron releasing device, and the supercharging device, the water activating device, the hydrogen enriching device and the electron releasing device are sequentially connected through a water supply pipe. The water activating device comprises a first filter cartridge, and energy spar and projectile natural ore are arranged in the first filter cartridge; the hydrogen-enriching device comprises a second filter cartridge; a combined multifunctional health-preserving hydrogen-enriching water sheet and a composite medical stone ceramic ball are arranged in the second filter cartridge; the electron release device comprises an inner ribbed tube, and a combined material composed of a composite tourmaline ceramic ball and an electrode metal band is placed in the inner ribbed tube. The active hydrogen generator can prepare a large amount of active hydrogen in a lasting, safe and environment-friendly manner, and third-party detection data shows that the content of the active hydrogen in water treated by the active hydrogen generator reaches 5-8 PPm.

The embodiment of the invention provides a dull polish radiation grain manufacturing technology. Radiation grains are machined on the surface of a sheet; the surface of the sheet with the radiation grains is subject to sand blasting treatment; the sheet subject to sand blasting treatment is polished; the polished sheet is subject to standing oxidation treatment; dull polish radiation grains are formed on the surface of the sheet; the embodiment of the invention further provides a shell of terminal equipment. In conclusion, the grain effect that the radiation grains and dull polish are overlapped is formed, the decoration effect is novel and unique, and the texture decoration can be effectively improved; the dull polish radiation grains are good in vision effect and soft in reflected light, the grains have the regularity and smooth hand feeling, and use experience of a user is effectively improved; particularly, the grains manufactured through the manufacturing technology are applied to the metal shell of a terminal, and the use effect of the grains is more prominent; meanwhile, the technology is simple in step and short in manufacturing procedure, and the production efficiency is effectively improved.

The invention belongs to the technical field of intermediate- and low-level radioactive waste treatment and relates to an intermediate- and low-level radioactive waste treatment method. The intermediate- and low-level radioactive waste treatment method is achieved in an intermediate- and low-level radioactive waste treatment device and is used for treating organic combustible waste which contains radioactive substances and is generated by hospitals, factories, research institutions and nuclear power plants. The sludge volume reduction and the harmless treatment of the intermediate- and low-level radioactive waste are achieved. The sludge volume reduction rate is more than 95%. The difficulties of big deposit volume and difficult storage of the intermediate- and low-level radioactive waste are solved. Firstly, heating equipment is started, then a burner is started, then a spray water scrubber is started to carry out pre-treatment, then feedstock is carried out, the waste is pyrolyzed, burned, and experiences catalytic reaction, and finally, is purified and discharged. The process is simple in method, reliable in principle, high in sludge volume reduction rate, good in curing effect, environmentally friendly in application, low in investment and operation costs, energy-saving and environmentally friendly, and has a good economic benefit and a wide market prospect.

The invention belongs to the technical field of fourth-generation lead bismuth cooling fast reactor structural materials, and particularly relates to a preparation method of a ferrite martensite steel ladle shell pipe. The ferrite martensite steel ladle shell pipe comprises the components of 0.15%-0.25% of C, 0.30%-0.8% of Mn, 0.40%-1.20% of Si, 10.5%- 12.5% of Cr, 1.0%-2.5% of W, 0.10%-0.40% of V, 0.10%-0.40% of Ta, 0.005%-0.08% of Zr, 0.005%-0.05% of La, 0.008%-0.04% of N, and balance Fe and impurities. The preparation method of the ferrite martensite steel ladle shell material comprises the following process steps of (1) determining the alloy components; (2) smelting; (3) casting; (4) forging; (5) extruding; (6) pipe blank machining and heat treatment; (7) multi-pass cold rolling and intermediate heat treatment of the alloy; and (8) final heat treatment of the pipe. According to the preparation method of the ferrite martensite steel ladle shell pipe, through the innovative component design, the optimized pipe machining deformation process and the heat treatment technology, the microstructure of the material is improved, grains are refined, and therefore the comprehensive performance of the alloy is improved.