Method for producing nuclear reactor fuel microelements
FIELD: nuclear power engineering; nuclear reactor fuel microelements covered with four-layer shielding coating.
SUBSTANCE: proposed method involves sequential fluid-bed deposition of coating layers onto fuel microspheres. First low-density pyrocarbon layer is deposited by pyrolysis of acetylene and argon mixture of 50 volume percent concentration at temperature of 1450 °C. 85 - 95 % of second layer is deposited from high-density pyrocarbon by pyrolysis of acetylene and argon mixture of 40.0 - 43,0 volume percent concentration, and of propylene and argon mixture of 30.0 - 27.0 volume percent concentration at temperature of 1300 °C; 5 - 15 % of coating is deposited by pyrolysis of propylene and argon mixture of 5.0 - 10.0 volume percent concentration doped with 0.5 - 1. 5 volume percent of methyl trichlorosilane. Third layer of silicon carbide is deposited by pyrolysis of methyl trichlorosilane and argon mixture of 2.5 - 3.0 volume percent concentration in hydrogen-argon mixture at temperature of 1500 °C. Upon deposition this layer is treated with hydrogen at temperature of 1750 -1800 °C for 20 - 30 minutes. 90 - 95 % of fourth layer is deposited by pyrolysis of acetylene and argon mixture of 40.0 - 43.0 volume percent concentration and of argon and propylene mixture of 30.0 - 27.0 volume percent concentration at temperature of 1300 °C. Upon deposition of 90 - 95 % of fourth-layer pyrocarbon coating thickness 5 - 10 % of coating is deposited by pyrolysis of propylene and hydrogen mixture of 3.0 - 5.0 volume percent concentration.
EFFECT: enhanced service life of fuel microelements due to reduced damage probability during their manufacture and in service.
1 cl, 6 dwg, 1 tbl
The invention relates to the field of nuclear energy, in particular to microwell high temperature gas cooled reactors (HTGR) high safety of operation.
One of the ways to improve the safety of operation of nuclear reactors is the use of fuel elements (cartridges), in which the fuel is localized in the microvolume of spherical particles of fissionable material, each of which has a protective coating of non-fissile material with characteristics that are optimized in accordance with the type of reactor and its operation conditions [Kotelnikov RB, Bashlykov S.N., Chestnut A.I., Menshikov I.E. high Temperature nuclear fuel. Ed. 2-E. M.: Atomizdat, 1978, 432 S.].
Regardless of the type of design of the fuel rods of the nuclear fuel in all types of HTGR is in the form of microspherical particles with layers of protective coating so-called microtalon-MT.
In modern MT HTGR number of protective layers on the fuel microsphere (TM), as a rule, does not exceed four (figure 1):
- first - low-density (buffer) layer of pyrocarbon (Rus);
- the second internal high-density isotropic eng;
third - silicon-carbide (SiC);
- fourth outer high-density isotropic eng.
The main task of the buffer Rus is providing free volume of the gaseous products of Deleni the (GPA) and rauhouse under irradiation TM, reducing thermal stresses due to differences in coefficient of linear thermal expansion of the material TM and subsequent coatings, as well as protection internal Rus and SiC layer from damage by fission fragments.
Internal high-density isotropic Rus is a barrier for GPA and most solid products division (TPD). His task is to protect the SiC layer from the effects of the fission fragments and protection of TM against the penetration of chlorine in the deposition of a layer of SiC.
The SiC layer is the main diffusion barrier for TPD, and also ensures the durability of the coating in General. Experimental studies show that the integrity of the SiC layer provides retention of almost all (maybe with the exception of the silver isotopes) of fission fragments at the required level.
Outer high-density isotropic Rus is an additional diffusion barrier and protects the SiC layer from mechanical damage during subsequent processing steps with MT.
In the irradiation process, the MT is the number of physical and chemical transformations, which can cause the destruction of the SiC layer and the coating as a whole, which will lead to increased leakage of fission products. Under normal operating conditions most of the HTGR (temperature exposure ˜900-1300°, fluence fast neutrons ˜4·1021n/cm2 and deep burnup fuel, the main factors determining the destruction of the coating MT are:
I. the Development of mechanical stresses in power coating layers under irradiation.
II. Chemical interaction of fission products with coating material (oxidation Rus, the interaction of SiC, for example, with palladium and so on).
III. The damaging effects of irradiation on materials surfaces.
IV. The presence of initial defects in the coating after fabrication MT, as well as residual stresses in the layers of the coating and on the border between the layers, causing the formation of additional defects in the fuel elements and in the early stages of irradiation, especially in conditions of thermal Cycling, temperature gradient and neutron flux.
The known method according to which the first buffer layer Rus precipitated on TM fluidized bed at a temperature of pyrolysis 1500°from acetylene (C2H2), and the second high-density isotropic Rus from acetylene-propylene mixture at 1100-1300° (U.S. Pat. U.S. No. 3554783, IPC 7 G21C 3/00).
The known method, whereby high-density isotropic pyrocarbon precipitated in a fluidized layer by pyrolysis of propane, propylene (C3H6or butadiene at a temperature of 1250-1300° (U.S. Pat. France No. 1593145, IPC 7 G21C 3/00).
The known method according to which a layer of silicon carbide precipitated in the fluidized bed when the temperature 1650± 25°and the concentration of methyltrichlorosilane (CH3SiCl3in the hydrogen of 2.5% vol. (Voice E.H., Scott V.C. The formation and structure of silicon carbide pyrolytically deposited in afluidized bed of microspheres, In.: Special Ceramics 5, Eds P. Popper at al. The British Ceramic Research Assoc., 1972, p.1-32).
Known deposition method is a four-layer coating in a fluidized bed TM, according to which the first buffer eng produced by pyrolysis With2H2at a temperature of 1250°With the second high-density isotropic eng produced by pyrolysis of C2H2-C3H6mixture at a temperature of 1300°With the third SiC layer produced by pyrolysis of CH3SiCl3at a temperature of 1500°and the fourth high-density isotropic eng produced by pyrolysis With2H2-C3H6mixture at a temperature of 1300° (Huschka H., Vugen P. Coated fuel particles: requirements and status of fabrication ethnology. - Nuclear Technology, V.35, September, 1977, p.238-245).
The disadvantage of these methods is that when the four-layer deposition coatings on TM using the conditions specified for individual layers is possible uncontrolled damage to the fragile silicon carbide single MT in the party of particles. The likelihood of damage to the SiC layer in a separate MT increases significantly in the presence of residual stresses in the coating material, as well as growth defects, especially on the outer surface of the silicon carbide layer.
N is the most closest analog prototype of the proposed technical solution is the way, whereby fluidized bed TM at 1450°and concentration With2H250% vol. precipitated the first buffer layer Rus, at 1300°from a mixture of C2H2(40-43%) and C3H6(30-27 vol.%) precipitated the second high-density isotropic layer Rus, at a temperature of 1500°With a mixture of CH3SiCl3with hydrogen precipitated the third layer of silicon carbide, the fourth high-density isotropic layer Rus precipitated on the mode of the second layer (U.S. Pat. Germany No. 2626446, IPC 7 SS 11/02).
The disadvantage of this method, like the previous, is the emergence in the process of deposition of residual stresses in the four-layer coating, which are the cause of damage to the SiC layer (figure 2) and the fourth Rus (3) separate MT in a large array of particles at the production stage. The influence of residual stresses effect at early stages of irradiation, resulting in damage to the SiC layer in the form of bundles (figure 4) and the detachment of local areas of the second Rus layer from the SiC (figure 5), limiting the life of MT.
The destruction of at least one of the three power coating leads to an increase of the output PD of the MT and thereby limit the life of the latter.
The authors proposed technical solutions faced the challenge of increasing resource use MICROTEL nuclear reactor by reducing damage pokr is involved at the stage of coating deposition TM, as well as during their operation.
The problem is solved in that at the stage of obtaining microtalon nuclear reactor with four-layer protective coating, comprising the sequential deposition on fuel microspheres protective layer coating in a fluidized layer, after deposition of 85-95% of the thickness of the pyrocarbon coating of the second layer 5-15% cover precipitated by pyrolysis of propylene concentration in the mixture with argon 5,0-10,0% vol. with the addition of 0.5-1.5 vol.% methyltrichlorosilane, after deposition of the third silicon carbide layer hold his treatment in hydrogen at a temperature of 1750-1800°C for 20-30 min, and after deposition of 90-95% of the thickness of the pyrocarbon coating of the fourth layer, 5-10% coverage precipitated by pyrolysis of propylene concentration in the mixture with hydrogen 3,0-5,0%vol.
The causal link between the essential features and the technical solution is as follows.
The sequential deposition of each layer four-layer coating on TM in the fluidized layer, the following processes occur:
- at the stage of deposition of SiC between him and second Rus arise mechanical stresses caused by the difference in coefficient of linear thermal expansion of the contacting pairs. Moreover, for individual MT from a large array of particles these stresses can be significant. Under conditions of thermal Cycling of particles in key is present layer this will lead to an increase in the probability of damage to the SiC layer.
In the deposition of 5-15% coverage of the second pyrocarbon layer by pyrolysis of 5.0-10.0% vol.% propylene in mixture with argon with the addition of 0.5-1.5 vol.% methyltrichlorosilane formed the boundary layer of pyrocarbon-doped silicon, the coefficient of linear thermal expansion which is close to the value of the coefficient of linear thermal expansion of SiC coating.
- upon receipt of SiC layer in it there are residual stresses, relaxation whose deposition is virtually impossible. In terms of the stress state increases the likelihood of damage in thermal Cycling conditions in a fluidized bed, and in the early stages of irradiation MT.
Treatment in hydrogen SiC layer, when it is the outer coating on the particle at a temperature of 1750-1800°C for 20-30 min promotes relaxation of residual stresses therein due to thermal creep.
- Rus outer layer composed MT performing a protective function for the protection of SiC from mechanical damage, experiences tensile stress. The tear resistance of external Rus layer, in conjunction with other characteristics of the material, significantly depends on the quality of its surface, which is the absence of Macrovision, macropores of diameter greater than 1000 Å etc.
In conditions, when 5-10% of the outer PN the layer precipitated by pyrolysis of propylene concentration in the mixture with hydrogen 3,0-5,0%vol., forms a smooth, without noticeable protrusions of the surface with a predominant concentration of closed pores with a diameter of 60-200 Å.
An example implementation of technical solutions
Fuel microspheres of uranium dioxide with a diameter of 500 μm are precipitated in a fluidized bed at a temperature of pyrolysis 1450°With the first buffer Rus layer from C2H2-Ar at concentrations2H250% vol. and the total gas flow 1500 l/h
After deposition of the desired thickness of the buffer Rus stop filing With2H2and the particles are supported in a state of fluidization due to the inert carrier gas argon.
Due to the reduction applied to the heater electric power, reduce the temperature of the fluidized bed to 1300°and feed in a reaction zone a mixture With2H2(40%vol.) and C3H6(30 vol.%) with argon at a total gas flow of 1500 l/h precipitated 85-95% of the thickness of the second Rus layer. After that, at constant temperature, stop the supply of the reaction gases (C2H2and C3H6), and the remaining 5-15% of the thickness of the doped silicon of the second layer precipitated by pyrolysis of propylene in mixture with argon 5,0% vol. with the addition of 0.5 vol.% methyltrichlorosilane.
The third layer of silicon carbide precipitated at a temperature of 1500°from a mixture of methyltrichlorosilane with hydrogen at a concentration of CH3SiCl32,0 is B.% and the flow of hydrogen on fluidization 1600 l/h After deposition of the desired thickness of the SiC layer stop the flow of CH3SiCl3in the reaction zone. The particles are in a state of fluidization in the reaction zone due to the consumption of hydrogen in the amount of 1600 l/h After that due to the increase applied to the heater electric power particles are heated to a temperature of 1800°aged at this temperature for 20-30 minutes
After reducing the temperature of the fluidized bed to 1300°from a mixture With2H2(40%vol.) and C3H6(30 vol.%) with argon precipitated 90-95% of the thickness of the fourth Rus layer. The total gas flow is 1500 l/h stop flow in the reaction zone With2H2and C3H6and the total flow is compensated by the increase of hydrogen supply. The remaining 5-10% of the thickness of the fourth layer at a constant temperature of 1300°precipitated by the pyrolysis of propylene concentration in the mixture with hydrogen to 3.0 vol.%.
Comparison of deposition conditions four-layer protective coating and operational characteristics of MT obtained by a known method, with MT on the proposed technical solution is given in the table.
As follows from the table, the proposed method of obtaining microtalon nuclear reactor (examples 2, 3, 4) in comparison with the known method (example 1) provides increased ESRC operation due to higher radiation resistance of the second Rus layer, less damage SiC and external Rus layers. With exorbitant parameters (examples 5, 6) the operating characteristics of the MT decline sharply.
The method of producing microtalon nuclear reactor with four-layer protective coating, comprising the sequential deposition on fuel microspheres layers of coating in a fluidized bed, in which the first layer of low-density pyrocarbon precipitated by the pyrolysis of acetylene concentration in the mixture with argon 50% vol. at a temperature of 1450°, 85-95% of the second layer of high-density pyrocarbon precipitated by pyrolysis of a mixture of acetylene concentration in the mixture with argon 40,0-43,0% vol. and propylene concentration in the mixture with argon 30,0-27,0% vol. at a temperature of 1300°With, a third layer of silicon carbide precipitated by pyrolysis of methyltrichlorosilane with a concentration in the mixture of the hydrogen-argon 2,5-3,0% vol. at a temperature of 1500°C and 90-95% fourth layer of high-density pyrocarbon precipitated by pyrolysis of a mixture of acetylene concentration in the mixture with argon 40,0-43,0% vol. and propylene concentration in the mixture with argon 30,0-27,0% vol. at a temperature of 1300°C, characterized in that after deposition of 85-95% of the thickness of the pyrocarbon coating Deut the layer 5-15% cover precipitated by pyrolysis of propylene concentration in the mixture with argon 5,0-10,0% vol. with the addition of 0.5-1.5 vol.% methyltrichlorosilane, after deposition of the third silicon carbide layer hold his treatment in hydrogen at a temperature of 1750-1800°C for 20-30 min, and after deposition of 90-95% of the thickness of the pyrocarbon coatings fourth layer of 5-10% coverage precipitated by pyrolysis of propylene concentration in the mixture with hydrogen 3,0-5,0%vol.
FIELD: nuclear engineering, in particular, engineering of micro heat-exhausting elements for nuclear reactors.
SUBSTANCE: first layer of micro heat-exhausting element with four-layer protective cover is made of SiC-PyC composition with content of 1,0-10,0 % of mass of silicon carbide with thickness of layer equal to 0,02-0,2 of diameter of fuel micro-sphere, second layer is made of SiC-PyC composition with content of 20,0-45,0 % of mass of silicon carbide with thickness of layer equal to 0,03-0,40 diameter of fuel micro-sphere, third layer is made of silicon carbide, while fourth layer is made of titanium nitride with thickness equal to 0,01-0,08 of diameter of fuel micro-sphere.
EFFECT: increased exploitation resource of nuclear reactor due to increased corrosion resistance and radiation stability.
3 dwg, 1 tbl
FIELD: nuclear power engineering; manufacture of fuel elements and their claddings.
SUBSTANCE: each weld of cladding and its plug are tested in facility equipped with units for clamping and revolving the claddings, scanning with carriage using weld inspection piezoelectric transducer and piezoelectric transducer for measuring wall thickness in measurement region, immersion bath, ultrasonic pulse generator, ultrasonic pulse receiver, microprocessor, analog-to-digital converter switch, and random-access memory.
EFFECT: enhanced quality of fuel elements and their operating reliability in reactor core.
1 cl, 1 dwg
FIELD: nuclear power engineering; fuel rods for water-moderated water-cooled reactors.
SUBSTANCE: proposed fuel rod designed for use in water-cooled water-moderated power reactors such as type VVER-1000 reactor has fuel core disposed in cylindrical can. Outer diameter of fuel rod is chosen between 7.00 . 10-3 and 8.79 . 10-3m and fuel core diameter is between 5.82 . 10-3 and 7.32 . 10-3m and mass, between 0.93 and 1.52 kg, fuel core to fuel rod length ratio being between 0.9145 and 0.9483.
EFFECT: reduced linear heat loads and fuel rod depressurization probability, enlarged variation range of reactor power, optimal fuel utilization.
7 cl, 3 dwg
FIELD: nuclear engineering; welding tubular cans of fuel elements to plugs.
SUBSTANCE: proposed method for sealing fuel element includes feeding can and plug to welding chamber, creating atmosphere in this chamber capable of shielding welded joint from oxidation, compressing can and plug ends followed by their welding using for the purpose nonsplit chamber whose unconfined space is smaller than that of can interior, feeding plug to welding chamber for its welding to can end, shielding atmosphere being permanently maintained within chamber. Shielding atmosphere is created by continuously blasting chamber with shielding gas using directly welded parts and pre-evacuation of enclosed space formed in the process, followed by its feeding with inert gas.
EFFECT: enhanced welding productivity, weld quality, and, hence, fuel element quality.
4 cl, 3 dwg
FIELD: production of uncontaminated mixed oxide fuel rods for atomic engineering.
SUBSTANCE: proposed method involves manufacture of uncontaminated MOX fuel rods from pellets in shielding chamber. The latter is held at pressure lower than indoor atmospheric value. Pellets are charged in stacked condition into can provided in advance with first plug on one of its two ends. Various structural components, such as hold-down spring, are charged. Second plug is installed on other end of can and held in position by circular weld, in particular when it is inserted in mentioned can without clamp. Parts of mentioned can or respective rod are at least once inspected for contamination. Safety chamber is divided into certain number of adjacent compartments. Each compartment communicates with adjacent one through sealed passage for can. Some of such passages are relatively aligned to provide for can movement along its longitudinal axis. Cans being charged with pellets are introduced with their open end forward into first compartment through sealed passage or inlet opening of compartment. Cans are moved along axis between sequential compartments until their open end occurs in last compartment. In the latter can is charged with pellets and, if necessary, with various structural members other than hold-down spring through its open end. Upon completion of charging can is partially pulled out along axis to transfer its open end to preceding compartment. In the latter can is at least partially cleaned and checked for probable contamination by pellets in the course of their charging or by atmosphere of last compartment. After that cans are moved to admit their open end to next compartment. Hold-down spring is installed and second plug is fitted in open end within this compartment. Then other required operations are made in this compartment or in another one involving additional movement of can. Parts of rod contaminated in last compartments are checked for condition and potentially decontaminated, as required, in first or second compartment. Rod is removed from first compartment or is crosswise displaced to other shielding chamber through first compartment that joins shielding chambers together. The degree of contamination stepwise changes between different compartments starting from no or negligible dirt in first compartment up to heavy contamination in last one. Gas supplied to these compartments is chosen from group incorporating air, nitrogen, helium, argon, and vacuum. Pressure within compartment is varied in steps to control leakage starting from high pressure in first compartment down to lowest pressure in the last one. In addition, device is proposed for producing uncontaminated MOX fuel rods.
EFFECT: enhanced safety for personnel engaged in manufacture of mixed oxide fuel rods.
19 cl, 12 dwg
FIELD: nuclear power engineering; fuel compositions for nuclear-reactor fuel elements.
SUBSTANCE: can of desired size is filled with finely dispersed fuel and in addition with material forming solid matrix at temperature equal to or higher than fuel melting point. This can filled with finely dispersed fuel and material forming solid matrix is heated to temperature equal to or higher than fuel melting point is heated and cooled down.
EFFECT: enhanced fuel density and resistance to destruction at meltdown accidents.
7 cl, 2 dwg
FIELD: mechanical engineering; welding; nuclear engineering.
SUBSTANCE: invention relates to manufacture of fuel elements of nuclear power stations which are sealed by resistance butt-welding. Proposed method of welding of fuel element jacket with plug comes to placing end of jacket with depression into welding equipment with preset electric resistance value and welding-in of plug into jacket wall to depth not less than twice thickness of jacket wall, with control of parameters of welding rate. Welding is carried out at rates providing distribution between areas of inner, found under jacket and outer, metal-fin forced out of butt joint of section at ratio not exceeding 3. Ratio of areas of sections of inner metal-fin arranged at two sides in any diametral section of weld joint made along its axis does not exceed two.
EFFECT: improved operation reliability of fuel elements owing to quality forming of weld joints.
1 ex, 2 dwg
FIELD: mechanical engineering; welding; nuclear engineering.
SUBSTANCE: invention relates to resistance butt-welding of tubular jackets of fuel elements with plugs. According to proposed method, end of pipe and end of plug are fixed in electrodes. Ends of pipe and plug whose outer diameter is greater than inner but smaller than outer diameter of pipe are compressed. Relative heating of pieces by welding current is carried out with subsequent driving plug into pipe. Welding is done mainly by heating of plug. Seating place is formed in process of displacement of plug between surface of its welded-in part and inner surface of pipe in direction of plug travel out of zone of thermal influence in pipe jacket. Larger part of fin formed at welding, and zone with maximum structural changes caused by thermal influence are brought outside. Zone with maximum structural changes is arranged out of zone of weld joint, and fin brought out is used to form smooth mating between outer surface of pipe and plug.
EFFECT: improved operating qualities of welded joints and their manufacturability.
1 ex, 2 dwg
FIELD: mechanical engineering; welding nuclear engineering.
SUBSTANCE: invention relates to methods of resistance butt welding for sealing of jackets of fuel elements of nuclear reactors and in process of manufacture of clusters of fuel elements. Method comes to compressing pipe and plug by welding force directed along axis of pipe and plug, heating them by electric current with subsequent welding-in with deepening of plug into pipe. Diameter of plug on section of formation of weld seam is greater than inner diameter of pipe, but is smaller than outer diameter of pipe. Welding current and force is applied to plug in different cross sections. Surface to apply welding current is arranged parallel to axis of plug and at angle of 90° to surface for application of welding force between said surface and part of plug welding into pipe.
EFFECT: provision of multipurposeness of method, improved quality of welding and service and technological characteristics of article.
FIELD: machine engineering, namely methods for contact-butt welding of tube with plug for making fuel elements of nuclear power stations.
SUBSTANCE: method comprises steps of fixing tube at embedding tube end in opening of welding fitting having predetermined value of electric resistance; placing plug having portion welded in tube wall and outer portion in electrode for supplying welding current to outer portion of plug; compressing parts by applying welding effort; heating parts by means of welding electric current and welding them. Outer portion of plug has several parts; its part adjacent to portion welded into tube wall has diameter exceeding diameter of said part but less than diameter of opening of welding fitting. At welding process part of outer portion of plug adjacent to portion welded into tube wall is at least partially introduced into opening of welding fitting for forming annular gap between said part of outer portion and tube end. Said annular gap is filled with outer burrs. Part of outer portion of plug that is not adjacent to portion welded into tube wall has diameter exceeding diameter of opening of welding fitting.
EFFECT: improved characteristics of articles, enhanced versatility of method.
4 cl, 3 dwg, 1 ex
FIELD: mechanical engineering; welding.
SUBSTANCE: invention relates to resistance butt-welding of pipe with stopper at sealing of fuel elements of nuclear power stations. Proposed device is electrode in form of chuck with central hole, provided with current supply surface and surface to transmit welding force. Current supply and welding force transmitting surfaces of electrode are separated and arranged at angle relative to each other. Current supply surface is arranged parallel to axis of central hole. Surface to transmit welding force is made of dielectric material. Groove is made on current supply surface of axial hole of electrode.
EFFECT: improved quality of welded joint.
3 cl, 1 dwg
FIELD: mechanical engineering; manufacture of devices for contact butt welding of pipes with plugs for sealing rod-type fuel elements of nuclear reactors.
SUBSTANCE: proposed method consists in stacking the current lead, stop-cooler made from set of metal plates at increased electric resistance and holder made from dielectric material. Stack thus made is subjected to machining and to aging by welding the specimens. Stop-cooler is electrically shunted by means of plate-type shunts located in holes made over perimeter of device. Plate-type shunts are rolled in cylinder and are fixed in holes by releasing deformable electric plugs fitted in these holes.
EFFECT: reduced labor consumption; enhanced operational stability; extended functional capabilities.
2 cl, 1 dwg
FIELD: nuclear power production, namely apparatuses for resistance butt welding of rod fuel elements of nuclear reactors.
SUBSTANCE: apparatus includes welding chamber, mechanisms for fluid-tightening it, apparatus for feeding welded parts of fuel element to welding zone, mechanisms for gripping, fixing welded part and for supplying electric current to them with respective drives, pneumatic drive for creating welding pressure. Welding chamber is in the form of built-up structure that is not open at operation of welding apparatus and it includes units for feeding envelope and plug of fuel element to welding zone. Apparatus includes additional pneumatic grip that is spaced from electrode of envelope by distance preventing excess displacing of its end caused by axial shift and lengthwise bending in said zone.
EFFECT: enhanced efficiency and improved stability of welding process, high operational reliability of apparatus in condition of high demands made to biological safety.
3 cl, 1 dwg
FIELD: atomic power engineering.
SUBSTANCE: device has welding chambers having apertures for inputting covers for pressurization, which concurrently are output apertures of heat-conductive elements, welding chambers electrodes, power source, transporting module for transverse product feed, common control system with blocks for parallel and serial connection, device for forming a break in secondary contour. Welding chambers are placed in parallel to each other at distance from each other, determined from formula S=t(m k+1), where S - distance between chambers axes, t - step of transport module, k - number of chambers in device equal to number of steps of transporting module in each singular step thereof, m - any integer starting from one, and control systems connected through parallel connection block to working tools of device of same names, and through block for serial connection to welding force drive and to device for forming break in secondary contour of power source, as well as to power source connected in parallel to welding chambers electrodes.
EFFECT: higher efficiency.
4 cl, 1 dwg