Inspection and sorting-out line for fuel elements
FIELD: atomic industry.
SUBSTANCE: proposed line is provided with computer-aided system for contactless control of flaw depth and profile on surface of fuel element can and on end parts including sorting-out device that functions to reject faulty fuel elements. This line is characterized in high capacity and reduced labor consumption.
EFFECT: enlarged functional capabilities, improved quality of fuel elements.
1 cl, 2 dwg
The invention relates to the nuclear industry and can find application in the manufacturing of fuel elements (FE) and build them into fuel assemblies (FA).
It is known that the fuel Rods are products for which the probability of failure must be extremely small, i.e. it demands high reliability. The most important parameters that are continuously monitored it the maximum allowable size of defects in the membranes, the geometric dimensions of the shells and the continuity of the column of fuel in the fuel rod (see Development. The construction and operation of fuel cell power reactors. Book 2. Edited Fgurative. - M.: Energoatomizdat, 1985, p.236). The surface quality control of pipes made of zirconium alloys and stainless steels up to this time is held by the visual method. The operation control time-consuming and inefficient. Assessment of the quality of the surface of the pipe subjective. When conducting a visual inspection usually use a set of control samples or standards of appearance, representing the pipe pieces with the most characteristic defects. As an example, in table. 21.3 description of the main defects (see ibid pp.261).
Closest to the technical essence and the achieved effect is the line of control and inspection of fuel is a separate estimate, contains the installation mechanism of the transport cassette with fuel elements for nuclear reactors VVER-1000 or VVER-440 with issuing them on a tilt table and a piece on the conveyor, along which technological sequence posted by means of control and inspection in the form of a gamma radiation source with photosensors detecting internal defects of fuel pellets, the length of a column of fuel pellets, the presence of retainers, the total gap between the fuel pellets, raspakoval output control defective fuel element in the container drive means control of the diameter and curvature, raspakoval output defective fuel element with control in container-drive, inclined tables with selectors, kickers, sensors monitor whether the position of the fuel control element VVER-1000 or VVER-440 and installation mechanism of the transport cassette receiving controlled fuel elements (see Russian Federation patent RU 2170961 from 09.06.1999,, publ. 20.07.2001, CL 7 G 21 C 17/06, 07 C 5/00. The line of control and inspection of fuel elements). Line-prototype allows you to expand its technological capabilities and to monitor and sorting different length TVEL VVER-1000 and VVER-440 and to extend the area of drives.
However, the control externally the mu surface appearance TVEL for detecting defects of mechanical origin in the form of dents, cracks, scratches, burrs, sticking and technological origin in the form of spots of oxide corrosion origin, dirt, darkening etc. is carried out by the visual method. The operation control time-consuming and inefficient. Assessment of the quality of the surface of the fuel rod is subjective. A large variety of types of defects is extremely complicates the development of instrument control methods, however, until now not yet created a means of control instruments that can replace the human eye (see Development, production and operation of fuel cell power reactors. Book 2, s). The technical challenge is to expand the technological capabilities of the line, increasing its productivity, quality of Fuel and reducing the complexity of the control.
This technical problem is solved in that the line of control and inspection of fuel elements containing the installation mechanism of the transport cassette with fuel elements for nuclear reactors VVER-1000 or VVER-440 with the issuance on the tilt table and individually on the conveyor, along which technological sequence posted by means of control and inspection in the form of a gamma radiation source with photosensors detecting internal defects of fuel pellets, the length of a column of fuel pellets, the presence of retainers, the total gap m is waiting for fuel tablets raspakoval output control defective fuel element in the container drive means control of the diameter and curvature, raspakoval output defective fuel element with control in container-drive, sloping tables with cut off the kickers, the sensors on the position of the fuel control element VVER-1000 or VVER-440 and installation mechanism of the transport cassette receiving controlled fuel elements.
According to the invention between the sloping tables with selectors, the kickers, the sensors on the position of the fuel control element on the conveyor wiring fuel element with control of the diameter and curvature of an automated system for contactless control of the depth and profile of the defects on the surface of the fuel cladding and end pieces with rubbercovered output defective fuel elements containing block system computer, monitor, block optomechanical with the illuminator and the block e, the block optomechanical contains a plate, on which the position sensor, optical table and placed on it by the interferometer, equipped with a video camera and an actuator moving a table, from the measuring arm of the interferometer on the stove strengthening the Jena front wall of the block opto-mechanical, on which is mounted a tray for placing a controlled heat-generating element, provided with a mechanism for fixing the position of the fuel element in the tray, and the electronic unit are devices control light, control of the phase modulator, the controller of the stepper motor, a uniform transducer pulses, the capacitor and the power source.
This implementation will allow to expand the technological capabilities of the line, increase productivity, quality Rods and reduce the complexity of the control.
The drawings show the line of control and inspection of fuel elements, in which figure 1 shows a General view of the line; figure 2 - automated system for contactless control of the depth and profile of the defects on the surface of the fuel element.
The line of control and inspection Below contains mechanism 1 installation transport cassette with heat-generating elements 2 for nuclear reactors VVER-1000 or VVER-440 with the issuance of the sloping table 3 and by the piece on the table 4, along which technological sequence placed controls and inspection 5 in the form of a gamma radiation source with photo-sensors detect internal defects of fuel pellets, the length of a column of fuel pellets, the presence of retainers, the total gap between the fuel pellets, raspakoval 6 is Yoda with control defective fuel element in the container-drive 7, means 8 controls the diameter and curvature, raspakoval 9 o defective fuel element with control in container-drive 10, the inclined tables 11, 12, 13, 14 with the selectors, kickers, sensors for position control of TVEL VVER-1000 or VVER-440 and the mechanism 15 installation transport cassette 5 acceptance is controlled by the fuel element.
Between the sloping tables 12, 13 with the selectors, the kickers, the sensors on the position of the fuel control element 2 on the conveyor 16 wiring the fuel element 2 with control 8 diameter and curvature installed an automated system 17 contactless control of the depth and profile of the defects on the surface of the fuel cladding 2 and end pieces with rubbercovered output defective fuel elements 2 containing block system computer 18, a monitor 19, block optomechanical 20 and the electronic unit 21, the block optomechanical 20 includes a plate 22, which is equipped with a position sensor 23, the optical table 24. located on the interferometer 25, equipped with a video camera 26 and the actuator move 27 table 24. Side of the measuring arm of the interferometer 25 in the plate 22 fortified the front wall of the opto-mechanical unit 20 on which is mounted the tray 28 to accommodate the controlled theprovides the corresponding item 2, equipped with a mechanism 29 of the fixing position of the heat generating element 2 in the tray 28, and the electronic unit 21 are devices: control illuminator 30, control of the phase modulator 31, the controller of the stepper motor 32, a uniform transducer pulses 33, the hub 34 and the power source 35, raspakoval 36 and container storage 37.
The line of control and inspection of Fuel elements is as follows.
The mechanism 1 is installed transport cassette with the fuel Rods 2 with the issuance of the sloping table 3 and apiece on the roller conveyor 4. On the roller table 4, the fuel Rods 2 are received in the tool 5 control and inspection for internal defects of fuel pellets, the length of their post, clamps, the total gap between tablets and rubbercovered 6 defective on these parameters, the fuel Rods have to be rejected in the container-drive 7. Fit the fuel Rods 2 are received in the tool 8 of the control of the diameter and curvature, where the defective fuel Rods 2 these parameters are rejected by rubbercovered 9 in the container drive 10.
Inclined tables 11, 12, 13, 14 are vehicle and drives the fuel rod 2. Controlled by these parameters, the fuel Rods 2 roller 16 serves in an automated system 17 contactless control of the depth and profile of the defects on the surface membrane of a fuel rod 2.
Measure the depth and profile of the defect is, or part thereof, located in a zone control system, carried out by scanning the surface area and data processing. The measurement results are displayed on the screen of the monitor 19 computer 18 at a convenient operator. In the control process of the fuel element 2 is placed in the tray 28 on the plate 22 and fixed by the fixing mechanism 29 and the sensor 23, the position of a fuel rod in the optical-mechanical unit 20.
Optical table 24 located on the interferometer 25, equipped with a video camera 26 and a light source 30, the actuator 27 moves vertically and horizontally and scans measured defect on the surface of the fuel rod 2.
Unit 21 e, containing the control device illuminator 30, the control device is a phase modulator 31, the controller 32 of the stepper motor, a universal Converter 33 pulses, the hub 34 and the source 35 power control unit 20 optomechanical in accordance with commands generated by the control program of the system, which is loaded in the computer 18.
Fit the fuel Rods 2 are loaded into the transport cassette mounted on the mechanism 15, and defective are removed from process rubbercovered 36 in the container drive 37.
The line of control and inspection of fuel elements containing the installation mechanism of the transport tapes with those who lofidelity elements with the issuance on the tilt table and individually on the conveyor, along which technological sequence placed controls and inspection to identify internal defects of fuel pellets, the length of a column of fuel pellets, the presence of retainers, the total gap between the fuel pellets, raspakoval output control defective fuel elements in the container drive means control of the diameter and curvature, raspakoval output defective fuel element with control in container-drive, sloping tables with selectors, kickers, sensors for position control of the fuel element and the installation mechanism of the transport cassette receiving controlled fuel elements, characterized in that between the sloping tables with selectors, the kickers, the sensors on the position of the fuel control element on the conveyor wiring fuel element with control of the diameter and curvature of an automated system for contactless control of the depth and profile of the defects on the surface of the fuel cladding and end pieces with rubbercovered output defective fuel elements containing block system computer, monitor, block optomechanical with illuminator and block opto-mechanical, containing a plate, on which the set is established with representation from the position sensor, optical table and placed on it by the interferometer, equipped with a camera and drive move a table from the side of the measuring arm of the interferometer on the stove reinforced front wall of the block opto-mechanical, on which is mounted a tray for placing a controlled heat-generating element, provided with a mechanism for fixing the position of the fuel element in the tray, and the electronic unit are devices control light, control of the phase modulator, the controller of the stepper motor, a uniform transducer pulses, the hub and the power source.
FIELD: nuclear power engineering; spacer grid manufacture for nuclear reactor fuel assemblies.
SUBSTANCE: spacer grid subchannels are produced from thin-wall tube by its chipless cutting into blanks with aid of rotary knife edges as they approach external and internal surfaces of revolving thin-wall tube; in the process operations of thin-wall tube division into blanks, chamfering opposing ends of blank, and burring them are combined.
EFFECT: enhanced yield, safety in operation, and productivity due to reduced number of operations.
3 cl, 6 dwg
FIELD: nuclear power engineering; manufacture of fuel elements for fuel assemblies of nuclear reactors.
SUBSTANCE: proposed process includes introduction of aluminum and silicon oxides in molded powder which form alumosilicate as result of pellet sintering aiding in enlargement of uranium dioxide grain to 10 - 20 μm and in increasing hardness compensated for by plasticity. In this way promising pelletized fuel of enlarged grain size and desired creep rate is obtained. Fuel pellets are noted for improved performance characteristics with respect to after-sintering and for enhanced effectiveness of fuel cycle in nuclear reactor due to enhanced burn-up.
EFFECT: enlarged yield and enhanced operating safety of nuclear reactor.
1 cl, 6 dwg
FIELD: the invention refers to the field of atomic energy and is used at producing ceramic nuclear fuel for heat-generating elements of nuclear reactors.
SUBSTANCE: mode of receiving fuel pellets for heat-generating elements out of uranium dioxide, including preparation of pressed powder out of uranium dioxide of ceramic variety, pressing and agglomeration of pellets. The pressed powder is received by way of decomposition of ill-conditioned sintered pellets in a mill with grinding bodies and adding 2-4 mass.% cellulating substance, and also out of uranium dioxide received according ADU-process, and out of uranium dioxide received by way of decomposition of ill-conditioned sintered pellets in a mill with grinding bodies and with adding 2-4 mass.% of cellulating substance.
EFFECT: allows to increase quality of cake nuclear fuel with simultaneous processing of spoilage in the form of ill-conditioned sintered pellets.
FIELD: nuclear power engineering; manufacture of fuel elements for water-moderated water-cooled reactors.
SUBSTANCE: in the course of conversion of uranium hexafluoride UF6 into uranium dioxide UO2 hexafluoride UF6 is supplied to combustion zone in air-hydrogen flame; then feed is changed over to new flow of gaseous hexafluoride until gaseous hexafluoride flow speed is reduced, and low-speed flow is conveyed to intermediate tank for condensation as soon as this tank is filled up (found by weighing), condensed hexafluoride is evaporated and gaseous hexafluoride flow is again conveyed to combustion zone. Fluoride is extracted from solid particles of uranium fluoride oxides by their heat treatment in hydrogen and superheated water vapor within revolving furnace at 650 - 660°C in first zone; deep extraction of fluorine from fluorine-containing uranium is effected in second zone at 660 - 665°C, and in third zone uranium dioxide powder is produced at 665 - 670°C by balling powder particles; uranium dioxide UO2 powder obtained in the process is cooled down in nitrogen medium to 18 - 20°C, magnetically separated, sifted through screen whose maximum mesh aperture is 1.25 mm, content of 70 μm fines of homogenization in nitrogen environment being not over 15%. Measurements are made using following formula: N = No x e-mpd, where N is number of photons recorded by detector in absence of fuel pellet; m is mass decay coefficient; p is fuel pellet density; d is thickness of fuel pellet zone under check. Fuel pellet density is found from formula p = (No/N)/md, and fuel pellets whose density is up to 10.4 and over 10.7 g/cm3 are rejected.
EFFECT: facilitated procedure.
1 cl, 1 dwg
FIELD: nuclear power engineering; repairs of nuclear reactor fuel elements.
SUBSTANCE: repairs of fuel assemblies where defective subchannels are detected include following procedures to restore their initial mechanical design: fuel elements and defective subchannels are removed form spacer grid section having defective subchannels. New serviceable subchannels are installed instead of defective ones, joined together, and secured to peripheral subchannels and to rim by resistance-spot welding using welding gun for the purpose. Fuel elements removed earlier are inserted in spacer grid subchannels and fuel assembly is washed out in hot demineralized water using live steam bubbling and hot air drying.
EFFECT: extended service life of fuel assemblies.
3 cl, 4 dwg
FIELD: nuclear power engineering.
SUBSTANCE: members used for fastening fuel element in hole of bottom end spacer grid are made in the form of shortened plug that has coaxial blind hole on its butt-end formed by annular walls expanded (burnished) in hole of larger diameter within bottom end spacer grid.
EFFECT: enhanced reliability of fuel assembly, reduced manufacturing cost and structural material input.
1 cl, 3 dwg
FIELD: nuclear power engineering, possibly automatic line for producing fuel elements of fuel assemblies of power nuclear reactors.
SUBSTANCE: aggregate is provided with detachable device for measuring electric resistance of fitting. Said device is arranged between collet chucks being in open position and it is made of two dielectric members spring-loaded one relative to other. End of one of said members has shape corresponding to contour of annular turning formed coaxially on end of collet chuck for plug. End of second member has shape corresponding to contour of annular turning formed coaxially on end of fitting in collet chuck for fuel element envelope. Said device has spring-loaded contacts for measuring electric resistance between fitting inside collet chuck and collet chuck itself. Caprolactam is used as dielectric material.
EFFECT: enhanced efficiency and quality of contact butt welding at sealing fuel element.
2 cl, 3 dwg
FIELD: nuclear power engineering; manufacture of fuel elements for fuel assemblies of power reactors.
SUBSTANCE: proposed process line has mechanism for weighing can charged with fuel pellets installed past retainer press-fitting mechanism; can is coupled through computer with mentioned weighing mechanism for outputting data on pure mass of pellets in can; γ-quanta detecting units and pellet enrichment automatic control installations are mounted on charged can guiding facility in the form of rolling train between its rollers throughout length of charged pellet stack; detecting units are disposed around pellet stack charged in can with collimation channels shifted throughout length of charged pellet stack; detecting units are provided with photoelectronic multipliers, spectrometers, and data acquisition, processing and outputting computer. Each detecting unit is provided with through hole passing can-displacement tungsten tube; shifted collimation channels are provided in top and bottom parts of tungsten tube; photoelectronic multipliers are disposed on butt-ends of detecting unit.
EFFECT: enhanced quality of fuel element manufacture.
3 cl, 3 dwg
FIELD: nuclear power engineering.
SUBSTANCE: proposed fuel assembly primarily designed for use in nuclear power reactors VVER-1000 and VVER-440 has composite bottom spacer grid built of at least two parts identical with respect to disposition of holes and total thickness of component parts equal to height of circular collar on bottom plug of fuel element, and tubular channel hole diameter for bottom plugs equal to diameters of lower ends of bottom plugs; the latter are secured in holes of aligned parts of bottom spacer grid by shifting component parts of bottom spacer grid relative to each other, by locking bottom plugs on circular collar of bottom plugs between annular projections of upper and lower parts of bottom spacer grid, and by aligning flow holes of bottom spacer grid component parts. Component parts of bottom spacer grid are rigidly fixed upon their shifting to bottom nozzle of fuel assembly in case of nonseparable type of assembly and loosely attached upon their shifting to bottom nozzle in case of separable type of assembly.
EFFECT: enhanced reliability of fixing fuel element plugs in bottom grid holes of separable and nonseparable fuel assemblies, reduced labor consumption for manufacture and assembly.
1 cl, 3 dwg
FIELD: nuclear power engineering; tubular dispersed-core three-layer fuel elements.
SUBSTANCE: proposed method includes production of powder mixture, powder mixing in plasticizer environment, cold molding in core billet with plasticizer, thermal sintering, hot molding-calibration of fuel core, core placing in can made in the form of sleeve with annular slot, calibration, hot molding through die, and drawing; inner surface of external can of sleeve is provided with longitudinal bulges and outer surface bears bulge location marks; fuel core is provided with longitudinal flats and placed in sleeve taking care to align bulges of the latter with core flats; in the course of drawing marks are aligned on arbor ribs.
EFFECT: enhanced stability of active layer and can thickness in shaping polyhedral fuel elements.
1 cl, 4 dwg
FIELD: analog computer engineering; verifying nuclear reactor reactivity meters (reactimeters).
SUBSTANCE: proposed simulator has m threshold devices, m threshold selector switches, m series-connected decade amplifiers, m electronic commutators, n - m - 1 series-connected decade frequency dividers, first group of m parallel-connected frequency selector switches, second group of n - m frequency selector switches, and group of n - m parallel-connected mode selector switches. Integrated inputs of threshold selector switches are connected to output of high-voltage amplifier and output of each threshold selector switch, to input of respective threshold device; output of each threshold device is connected to control input of respective electronic commutator; inputs of electronic commutators are connected to outputs of decade amplifiers and outputs are integrated with output of group of mode selector switches and with input of voltage-to-frequency converter; output of inverting amplifier is connected to input of first decade amplifier and to that of group of mode selector switches; input of first group of frequency selector switches is connected to output of voltage-to-frequency converter and to input of first decade frequency divider and output, to integrated outputs of first group of frequency selector switches and to input of division-chamber pulse shaper input; each of inputs of second group of frequency selector switches is connected to input of respective decade frequency divider except for last one of this group of switches whose input is connected to output of last decade frequency divider; threshold selector switches and frequency selector switches of first group, as well as m current selector switches have common operating mechanism; mode selector and frequency selector switches of second group have common operating mechanism with remaining n - m current selector switches. Such design makes it possible to realize Coulomb law relationship at all current ranges of simulator for current and frequency channels.
EFFECT: ability of verifying pulse-current input reactimeters by input signals adequate to signals coming from actual neutron detector.
2 cl, 1 dwg
FIELD: the invention refers to analytical chemistry particular to determination of general hydrogen in uranium dioxide pellets.
SUBSTANCE: the installation has an electrode furnace with feeding assembly , an afterburner, a reaction tube with calcium carbide, an absorption vessel with Ilovay's reagent for absorption of acetylene, a supply unit. The afterburner of hydrogen oxidizes hydrogen to water which together with the water exuding from pellets starts reaction with carbide calcium. In result of this equivalent amount of acetylene is produced. The acetylene passing through the absorption vessel generates with Ilovay's reagent copper acietilenid which gives red color to absorption solution. According to intensity of color of absorption solution the contents of general hydrogen are determined.
EFFECT: simplifies construction of the installation, increases sensitivity and precision of determination of the contents of hydrogen in uranium dioxide pellets.
2 cl, 1 dwg
FIELD: analyzing metals for oxygen, nitrogen, and hydrogen content including analyses of uranium dioxide for total hydrogen content.
SUBSTANCE: proposed analyzer depending for its operation on high-temperature heating of analyzed specimens has high-temperature furnace for heating uranium dioxide pellets and molybdenum evaporator; molybdenum evaporator is provided with water-cooled lead-in wire, and molybdenum deflecting screen is inserted between molybdenum evaporator and furnace housing.
EFFECT: simplified design of electrode furnace, reduced power requirement.
1 cl, 1 dwg
FIELD: identifying o spent fuel assemblies with no or lost identifying characteristics for their next storage and recovery.
SUBSTANCE: identifying element is made in the form of circular clip made of metal snap ring or of two metal semi-rings of which one bears identification code in the form of intervals between longitudinal through slits. Clip is put on fuel assembly directly under bracing bushing and clip-constituting semi-rings are locked in position relative to the latter without protruding beyond its outline. For the purpose use is made of mechanical device of robot-manipulator type. Identification code is read out by means of mechanical feeler gage and sensor that responds to feeler gage displacement as it engages slits. Identifying elements are installed under each bracing bushing.
EFFECT: ability of identifying fragments of spent fuel assembly broken into separate parts before recovery.
10 cl, 4 dwg
FIELD: nuclear power engineering.
SUBSTANCE: proposed invention may be found useful for optimizing manufacturing process of dispersion-type fuel elements using granules of uranium, its alloys and compositions as nuclear fuel and also for hydraulic and other tests of models or simulators of dispersion-type fuel elements of any configuration and shape. Simulators of nuclear fuel granules of uranium and its alloys are made of quick-cutting steel alloys of following composition, mass percent: carbon, 0.73 to 1.12; manganese and silicon, maximum 0.50; chromium, 3.80 to 4.40; tungsten, 2.50 to 18.50; vanadium, 1.00 to 3.00; cobalt, maximum 0.50; molybdenum, 0 to 5.30; nickel, maximum 0.40; sulfur, maximum 0.025-0.035; phosphor, maximum 0.030; iron, the rest.
EFFECT: enhanced productivity, economic efficiency, and safety of fuel element process analyses and optimization dispensing with special shielding means.
1 cl, 3 dwg
FIELD: operating uranium-graphite reactors.
SUBSTANCE: proposed method for serviceability check of process-channel gas gap in graphite stacking of RBMK-1000 reactor core includes measurement of diameters of inner holes in graphite ring block and process-channel tube, exposure of zirconium tube joined with graphite rings to electromagnetic radiation, reception of differential response signal from each graphite ring and from zirconium tube, integration of signal obtained, generation of electromagnetic field components from channel and from graphite rings, separation of useful signal, and evaluation of gap by difference in amplitudes of signals arriving from internal and external graphite rings, radiation amplitude being 3 - 5 V at frequency of 2 - 7 kHz. Device implementing this method has calibrated zirconium tube installed on process channel tube and provided with axially disposed vertically moving differential vector-difference electromagnetic radiation sensor incorporating its moving mechanism, as well as electronic signal-processing unit commutated with sensor and computer; sensor has two measuring and one field coils wound on U-shaped ferrite magnetic circuit; measuring coils of sensor are differentially connected and compensated on surface of homogeneous conducting medium such as air.
EFFECT: ability of metering gas gap in any fuel cell of reactor without removing process channel.
2 cl, 9 dwg
FIELD: minerals dressing.
SUBSTANCE: the offered inventions concern to dressing of minerals, in particular, to dressing of a ground mineral material. The technical result of the inventions is improved selectivity of separation of a source material by a choice of efficient way of separation and elimination of an effect of noises of a channel of registration and instability of the excitation system operation; improved automatic adjustment of the registration and excitation systems, reduction of an amount of used hardware and the time necessary for performance of the prestarting inspection and also provision of the automatic prestarting and periodic inspection and an increase of its reliability. For this purpose the separator contains means of delivery and transportation of the source material in a zone of inspection; a source of an exciting radiation; a photo-receiving device, and means of treatment of a signal of the luminescence including an analog-digital converter (ADC), a unit of the random-access memory (RAM), a register of a separation threshold and a microprocessor. In addition the separator is supplied with a register of delay and a synchronizer, the first output of which is connected to the input of the analog-digital converter start; the second output is connected to the input of the RAM; and its third output - with the input of the record of the microprocessor. The reading inputs of the random-access memory, the register of a threshold and the register of delay are connected accordingly to the first, second and third outputs of the microprocessor. The method of control over operation of the separator is based on a periodic use of its indicators in absence of a separated material for registration of intensity of their luminescence. In the capacity of an indicator they choose the air filling the volume of the separator, in the capacity of the way of separation - the normalized autocorrelation function (NACF) of a luminescence signal. At that they normalize the value of the NACF signal of the luminescence by its division by the result of integration of a square of a registered signal of a luminescence. Determine a threshold of separation equal to a threshold set at operation in a mode of separation. The value of the parameter of separation they choose so, that the value of NACF at the chosen value of the parameter exceeded the threshold.
EFFECT: the invention ensures improved selectivity of the source minerals separation, elimination of operational noises of the registration and other systems, automatic adjustment of the systems, reduction of hardware amount and time for preparation, increased reliability.
8 cl, 3 dwg