50 results about "Irradiated materials" patented technology

An article of manufacture comprising a radiation sensitive material, and a measuring scale that is part of the radiation sensitive material. A method of measuring at least one parameter relating to an irradiated material is also described. A radiation sensitive material including a measuring scale is exposed to radiation and at least one parameter relating to one or more exposed areas of the material is measured by reference to the measuring scale on the material.

A system for causing uniform ablation of irradiated material of living tissue while not causing damage below a predetermined depth where laser radiation is provided sequentially and continuously in a predetermined pattern is disclosed.

A CHMSL (16) or other lighting system feature of an automobile (10) includes a feature for presenting personal expressions in the form of words or symbols but is automatically deactivated when the regular vehicle lighting system is in use. The personal expression is fixed in a tangible medium by way of phosphor-coated indicia (34) placed within a UV impervious housing (18). A secondary UV light source (36) selectively energizes the phosphor-coated indicia (34) so that the irradiated material glows and is visible through a light transmissive screen (20). The light transmissive screen (20) is provided with a UV blocking agent so that harmful UV rays do not escape the housing (18). The phosphor-coated indicia (34) can be mounted on a removable transparent plate (30), on light dispersion optics (24, 26), or on the inner face of the light transmissive screen (20). A control circuit (42″) manages the primary light source (22) and the secondary UV light source (36) so that only one of the light sources can be energized at any one time.

The invention provides a clamped straight rod small sample creep testing method and an apparatus thereof. The testing apparatus comprises a heating module, a loading module, a clamping module, a displacement measuring module and an external support; and the testing method comprises the following steps: designing and making a clamped straight rod small sample, carrying out multiple creep tests of a material at a same temperature under different loads, establishing a steady state creep rate curve, obtaining a Kachanov-Rabotnov creep damage constitutive equation, and adopting a finite element to carry out parameter optimization. The small sample creep testing method provided by the invention solves the problems of difficult data parse and many testing influence factors of present small sample technologies, has the advantages of simple operation, high testing precision and low cost, and provides basic data for the exploitation of a new material, the high-temperature integrity evaluation of a service member and the performance evaluation of an irradiated material.

The invention provides a process for forming optical components and new optical materials utilizing electron beam irradiation. The process comprises selectively irradiating optical materials to alter their index of refraction gradient three dimensionally. With the inventive process, new optical materials can be created that have enhanced optical properties over the un-irradiated material. The invention also provides a process in which optical components can be fabricated without requiring a planar/multiple layer process, thereby simplifying the fabrication of these optical components. The inventive process uses a controlled electron beam to alter the properties of optical materials. By using the radiation of a controlled electron beam, controlled changes in the index of refraction gradient of optical materials can be obtained. Further, radiation of the electron beam can be used to create new optical materials from materials not previously believed to be suitable for optical applications. This is based not only on the refractive index change created in the material, but also upon the change in other material properties such as elimination of melt and reduced solubility in normal solvents. In these cases, the electron beam modifies and creates a new networks structure within the material, which enhances its optical properties and allows for the formation of useful physical properties necessary for the fabrication of useful devices (i.e., resulting in wholly new optical materials). It is also disclosed that the inventive process can be used to produce a spatially graded index of refraction within a material to enhance the performance of an optical waveguide which can lead to a number of novel structures.

The invention discloses a sample component and method for a nuclear power plant reactor pressure container irradiation inspection test. The component comprises a tensile sample, an impact sample and a compact tensile sample, wherein the tensile sample is used for acquiring the tensile strength, the yield strength, the elongation and the cross section reduction ratio of irradiated materials, the impact sample is used for acquiring impact toughness of the irradiated materials, the compact tensile sample is used for acquiring fracture toughness of the irradiated materials and provided with notches, circular portions and side grooves which are sequentially formed in a first side face and a second side face from top to bottom, and the notch with an isosceles trapezoidal section, the circular portions and the notch with a V-shaped bottom jointly form an extensometer placement space. The method includes the steps of sample preparation, sample loading, sample testing and result evaluation. Arrangement of a bent sample is canceled, the quantity proportion of the other samples is optimized, the shape of the compact tensile sample is optimally improved, and test failure risks in fracture toughness testing are decreased.

The invention discloses a low energy big flow and strong irradiation device for materials. The key points of the technical scheme of the device are as follows: the device comprises an air supply system, an air pressure monitoring device 2, a plasma generation system, a sample table 13, a laser heating system 6, a temperature measurement system 9, a vacuum extraction system 5, a water-cooling circulating system 4 and a power supply system. When the material surface is processed by the device, the irradiation environment of a nuclear fusion reactor can be effectively simulated, and further, changes of characteristic, structure and function of the irradiated material can be studied.

The invention relates to a double-light beam micro/nano optical manufacturing method which comprises the following steps: S1, providing manufacturing light according to the material properties of a to-be-irradiated processing material, so that the material properties of the to-be-irradiated processing material is changed under the irradiation of the manufacturing light; S2, providing auxiliary light according to the material properties of the to-be-irradiated processing material, wherein the auxiliary light can hinder the change in the material properties of the to-be-irradiated material underthe irradiation of the manufactured light; S3, regulating and controlling the manufacturing light and the auxiliary light, so that focal points distributed on a first local light field and a second local light field and formed by the manufacturing light and the auxiliary light on the to-be-irradiated material overlap in space, and a processing light field which is not superimposed by the second local light field and acts on the to-be-irradiated processing material is formed in the range of the first local light field. The manufacturing method provided by the invention can realize smaller feature size and higher resolution ratio, and a pattern and a structure manufactured have better mechanical property.

The invention discloses a vacuum acquisition device for an EUV (Extreme Ultraviolet) irradiation material test system and a corresponding test method, wherein the test system comprises an EUV light source chamber (A), a collection mirror chamber (B) and a sample chamber (C); the vacuum acquisition device comprises a vacuum pump unit and a vacuum gauge unit that are respectively connected to each chamber, a first gate valve and a second gate valve (A3, B3) that are connected between the chambers, a first gas source and a second gas source (A4, B4) that are used for communicating the first gate valve and the second gate valve (A3, B3), as well as a gas analysis unit (C5) that is connected with the vacuum pump unit (B1) of the collection mirror chamber (B) by a valve. The invention can evacuate each part of the test system, effectively prevent pollutants from dispersing from the EUV light source chamber and the sample chamber to the collection mirror chamber, and can measure the gas components in the sample chamber and the partial pressure when the vacuum pressure is unmatched.

The present invention provides a portable radiation generating device for generating high energy electron beam radiation and X-rays from a low voltage power source such as a battery (42). The pulse high voltage generator (40) includes a power supply (42) and a Tesla transformer (41). The Tesla transformer has at least one first capacitor (44), a primary coil (46), a secondary coil (48), and at least one second capacitor (50). The at least one second capacitor is disposed axially within the secondary coil. A control system (60) is connected to the pulsed high voltage generator (40) for selectively controlling the energy transfer from the pulsed high voltage generator (40) to the radiation generating device (22). The radiation generating means are used to generate pulses of electrons and X-rays. Each pulse has a duration of approximately 100 nanoseconds. The electrons and X-rays generated by the radiation generating device can be used to inactivate microbial contaminants or irradiate various materials.

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 relates to a comprehensive judgment method for performance irradiation ageing damage of an elastomer for nuclear power. The comprehensive judgment method particularly comprises the following steps of: (1) carrying out macro-performance test on an elastomer material, and preliminarily evaluating the ageing condition of each macro-performance of the irradiated material; (2) carrying out appearance observation on an irradiation sample, and judging the fracture mode is one or more reasons of ductile fracture, brittle fracture and the like by combining with a test result of the mechanical performance of the step (1); and (3) carrying out system analysis and testing on parts such as a tensile fracture surface and the interior of the material by virtue of multiple detection measures, and accurately judging the reasons of the ageing damage of the material by combining with a fracture appearance observation result of the step (2). By virtue of rapid analysis on typical modified rubber for the nuclear power under a ray irradiation condition, the reasons of the ageing damage of the elastomer material are accurately judged, and therefore, the targeted failure prevention and life prediction can be carried out. The comprehensive judgment method has application values in the evaluation on the service performance of other elastomer polymer materials in the fields of nuclear power, thermal power and petrochemicals, and the effective reference basis is provided for the selection and quality evaluation of materials in practical engineering application.

Disclosed herein are graphene quantum dot tagged water source treatment compounds or polymers, and methods of making and using. Also described herein are tagged compositions including an industrial water source treatment compound or polymer combined with a graphene quantum dot tagged water source treatment compound or polymer. The tagged materials are tailored to fluoresce at wavelengths with minimized correspondence to the natural or “background” fluorescence of irradiated materials in industrial water sources, enabling quantification of the concentration of the water source treatment compound or polymer in situ by irradiation and fluorescence measurement of the water source containing the tagged water source treatment compound or polymer. The fluorescence measurement methods are similarly useful to quantify mixtures of tagged and untagged water source treatment compounds or polymers present in an industrial water source.

The invention refers to a procedure for etching of materials at the surface by focussed electron beam induced chemical reactions at said surface. The invention is characterized in that in a vacuum atmosphere the material which is to be etched is irradiated with at least one beam of molecules, at least one beam of photons and at least one beam of electrons, whereby the irradiated material and the molecules of the beam of molecules are excited in a way that a chemical reaction predetermined by said material and said molecules composition takes place and forms a reaction product and said reaction product is removed from the material surface - irradiation and removal step.

In a process for the irradiation of strand-shaped irradiated material (19; 19a-e), in particular cable insulation or sheathing (31) capable of being cross-linked by irradiation, or tubes, hoses, or profile elements capable of being cross-linked by irradiation, with electron beams impinging transversely to the longitudinal axis of the irradiated material (19; 19a-e), which strike the irradiated material (19; 19a-e) from two fixed irradiation directions (R1, R2), located at an angle to one another which is other than zero and for preference is a right angle, a uniform irradiation is achieved in a simple manner in that a scanned electron beam (17) is created from an electron beam (11) in a scanner (12) by means of a scan device (13), which by means of a temporally-actuated back-and-forth slewing movement in a prescribed angle range creates a radiation fan transversely to the longitudinal direction of the irradiated material, and that the scanned electron beam (17) is deflected by a deflection magnet (16, 16') arranged between the scan device (13) and the irradiated material (19; 19a-e) in such a way for each scan angle of the irradiation field that it impinges on the irradiation material (19; 19a-e) to be treated from one of the two fixed irradiation directions (R1, R2).

The invention relates to a laser phase transition hardening method and a bionic camshaft with a hard phase prepared by the method. The laser phase transition hardening method comprises the steps: the surface of a workpiece is scanned by a laser beam with high-energy density, so that the surface temperature of the irradiated material rises to 10-20 DEG C higher than the solidus at high speed, and the surface of the heated area is heated to a semisolid state and then is rapidly cooled by a parent, thus a bionic unit body of which the microstructure is fine martensite is obtained, and the hardness can reach 690-770HV. A wearing surface layer with a soft and hard striped structure can be prepared on the cam surface of the camshaft by the method, and the hardness and the wear resistance of the cam surface are improved. The laser phase transition hardening method has the advantages of simple operation, little workpiece deformation and no defect, is suitable for the strengthening treatment of the camshaft, and is also suitable for the surface strengthening treatment of other workpieces made of 40Cr materials such as gears, sleeves, etc.

The invention discloses a preparation method of coal-based mesoporous activated carbon. The preparation method comprises the following steps: crushing raw coal to obtain pulverized coal, adding the pulverized coal, an activator, ethanol and a ball-milling ball into a planetary ball mill, and performing ball milling to obtain a mixture; activating the bal-milled mixture in a nitrogen atmosphere toobtain an activated material; adding the activated material into a supercritical device, soaking the activated material in a supercritical acetone-water system, then filtering, washing and drying theobtained system, adding the dried material into an alkaline solution, and performing ultrasonic soaking; and filtering and drying the ultrasonically soaked material, placing the dried material in a sealed glass tank, irradiating the material with an electron beam irradiation device, washing the irradiated material with water, and drying the washed material to obtain the coal-based activated carbon. The coal-based mesoporous activated carbon obtained by the preparation method has a high specific surface area and a high mesoporosity, and has a high adsorption value for methylene blue.

The invention discloses a tungsten-based columnar crystal high-entropy alloy plasma facing material and a preparation method thereof, and belongs to the field of nuclear fusion energy application. The tungsten-based columnar crystal high-entropy alloy is provided with columnar crystal grains with (001) orientation, and the grain size ranges from 10 micrometers to 70 micrometers. The high-entropy alloy comprises, by atomic percent, 20%-35% of W, 10%-25% of Ta, 10%-25% of Cr, 10%-20% of V, 5%-20% of Ti and 5%-20% of Y. The density of the tungsten-based columnar crystal high-entropy alloy can reach 99% or above, the purity of the tungsten-based columnar crystal high-entropy alloy exceeds 99.9%, the size of the columnar crystal can be controlled to be 10-70 microns, and fuel retention in a material after irradiation can be remarkably reduced. According to the tungsten-based columnar crystal high-entropy alloy, due to the high-entropy effect, the migration energy of interstitials and vacancies in the irradiated material is closer, so that the recombination rate of the interstitials and the vacancies is higher, and the neutron irradiation resistance of the material can be remarkably improved.