Process line for fuel element manufacture

FIELD: nuclear power engineering; manufacture of fuel elements for nuclear reactors.

SUBSTANCE: process line primarily used for manufacturing fuel elements for VVER-1000 and VVER-440 reactors has charged can weighing device built integral with can-and-plug assembly weighing device that determines net weight of charged can by internal components, box holding devices for discharging fuel pellets from rejected fuel element, destructive testing of helium pressure within can, and preparing specimens for metallographic inspection.

EFFECT: enlarged functional capabilities of line, improved quality of fuel elements, enhanced yield.

1 cl, 9 dwg

 

The invention relates to the nuclear industry and can find application in the manufacturing of fuel elements for nuclear pressurized water reactors.

It is known that fuel elements (Cartridges) are the most responsible and the most intense structures of the active zone of modern nuclear power reactor, so their manufacturing must meet the most stringent requirements.

It is known that the core of the fuel element reactor thermal neutron consists of a cylindrical metal alloy of zirconium, 1% niobium shell, inside of which is nuclear fuel in the form of dioxide enriched uranium 235, end fittings required for sealing sheath, clip, ensuring the location of nuclear fuel in the form of tablets in the desired position (see Development, production and operation of fuel cell power reactors. Book 1., Fegersheim, Ukiriguru, Issolvin, M.: Energoatomizdat. 1995, p.45). For pressurized water reactor VVER-1000 the length of the rod of a fuel rod is 3837 mm and a diameter of 9.1 mm, and for VVER-440 length is ~2500 mm and a diameter of 9.1 mm

Known for the automatic production line of fuel Rods containing devices:

- preparation of the casing for equipment with welding stub to one end about the shell,

- equipment of the column of fuel pellets in the open end of the shell,

- mounting clamps into the open end of the filled shell,

- sealing the open end of a filled shell feeder stub and weld it to the shell under the pressure of the inert gas under the shell,

control and sorting in the pressure inside the Fuel cladding placed after device closure,

control and inspection by the presence of internal components

- surface treatment,

control and grading curb fuel Rods in length and curvature, are placed in a single stream, equipped with a vehicle wiring device-to-device and device to output the defective fuel Rods (see Patent EP No. 0192137, IPC G 21 21/02, 1986).

Known automatic production line TVEL not provides accommodation in single process flow of the Stripping mechanism of the weld after welding stub to one end of the tube shell in preparation device shell to the equipment, resulting in concealment of possible defects in the weld, as the latter are detected after Stripping. In addition, the well-known lines may produce either Fuel for WWER-1000, or the Fuel of VVER-400 as they are different lengths - (3837 mm and 2500 mm), and the line provides for the production of fuel Rods of the same size.

Known for the automatic production line of fuel elements (see Russian Federation Patent No. 2070740, IPC G 21 21/02 from 17.05.94, published 20.12.1996, containing:

- installation preparation of membranes to the equipment of the fuel Rods, comprising an inclined rack table, along which technological sequence posted by mechanisms pieces of tubing with two parties in the amount of membrane for a fuel rod with a rotational drive and axial reciprocating movement, a mechanism to control the length of the tube shell in the form of rolling in the axial direction and fixed stops with sensors, a calibration mechanism rod one end of the tube-shell driven axial reciprocating movement adjacent to an inclined table sminia degreasing baths, preparation and drying of the inner and outer surfaces of the tubes of shell adjacent to the baths inclined rack table along which technological sequence posted mechanism mounting bracket into the grooved end of the tube wrapper, mechanism for weighting shell, the installation of electron-beam welding the caps to the shell, the Stripping mechanism of the weld, the mechanism of ultrasonic weld inspection and money transactions from mechanism to mechanism with automatic system, installation of wyposarzenia column of fuel pellets to open the first end of the shell, includes vibrating feeder feed fuel pellets on a horizontal cradle as guides for the formation of the pillars of fuel pellets, the control device the length of the pillars of fuel pellets with clipper-emphasis of the beginning of the pillars and the cutter-clamp the end of the pillars of fuel pellets made from individual cylinders for each post with the spring-loaded rods with elastic material on the end of the table adjacent to the installation of equipment with containers for laying them in the shells coaxially posts fuel pellets open end in the direction of the fuel pillars with a mechanism for stacking and feeding shells on equipment and removal of loaded shells,

device Stripping of the open end of the filled shell,

device mounting clamps into the open end of the filled shell,

- installation of sealing the open end of a filled shell feeder stub and weld it to the shell under the pressure of the inert gas under the shell,

- the mechanism of control and inspection by the presence of internal components

- installation surface treatment of a fuel rod with the oxidation of the surface of fuel cladding, equipped with a vehicle wiring device-to-device output defective fuel elements and control system.

Automatically the second line can be used either for the manufacture of Fuel for VVER-1000 reactor with a length 3837 mm, or for WWER-440 reactor with a length of 2500 mm, i.e. there must be two independent lines for Fuel of VVER-1000 and VVER-440, and the use of one line for the manufacture of fuel Rods of the VVER-1000 and VVER-440 without structural changes of the line is not possible, because:

1) on the operation sections of the tube in the size of the shell for TVEL VVER-1000 cut in the size of the shell VVER-440 requires design changes;

2) on the operation of measuring the length of the tube-shell you want to change the design of the rolling emphasis;

3) on the calibration operation will require elongation of the rod feed tube shell to calibrate one end;

4) on the operation of pressing the caps in the grooved end of the tube will need to modify the design of the pressing device, because there may be cases when the cover of the feeder may lie with the transfer because of the offset center of gravity and will need the device orientation, but otherwise possible marriage - fitting plugs into the shell crooked;

5) on the operation of the equipment requires a design change for the formation of a column of fuel pellets smaller length;

6) on the operation of equipment fuel pellets in the shell you want to change the design of the mechanism for feeding shell long dock with the lodgement of the formation of a column of fuel pellets and return the filled shell to its original position.

Most b is iscoe to the technical essence and the achieved effect is the automatic production line of fuel elements, contains:

- installation preparation of membranes to the equipment of the fuel Rods, comprising an inclined rack table, along which technological sequence posted by mechanisms pieces of tubing with two parties in the amount of membrane for a fuel rod from the actuator rotation and axial reciprocation, a mechanism to control the length of the tube shell in the form of rolling in the axial direction and fixed stops with sensors, a calibration mechanism rod one end of the tube-shell driven axial reciprocating movement adjacent to an inclined table adjacent bath degreasing, rinsing, and drying of the inner and outer surfaces of the tubes of shell adjacent to the baths inclined rack table along which technological sequence posted mechanism mounting bracket into the grooved end of the tube-shell feeder feeder stub on the position of the pressing mechanism of the weighing shell, the installation of electron-beam welding to the shell, the Stripping mechanism of the weld, the mechanism of ultrasonic weld inspection and posting from mechanism to mechanism with automatic system,

- installation of wyposarzenia column of fuel pellets in the open end of the shell, comprising a vibratory feeder feed fuel pellets on a horizontal cradle in the form of guides DL the formation of the pillars of fuel pellets, device control the length of the pillars of fuel pellets with clipper-emphasis of the beginning of the pillars and the cutter-clamp the end of the column of fuel pellets made from individual cylinders for each post with the spring-loaded rods with elastic material on the end of the table adjacent to the installation of equipment with containers for laying them in the shells coaxially posts open end in the direction of the fuel columns with the mechanism of stacking shells on equipment and removal of loaded shells,

device Stripping of the open end of the filled shell,

device mounting clamps into the open end of the filled shell,

- installation of sealing the open end of a filled shell feeder stub and weld it to the shell under the pressure of the inert gas under the shell,

- control mechanism and formation pressure within the shell of a fuel rod,

- the mechanism of control and inspection by the presence of internal components

- installation surface treatment of a fuel rod with the oxidation surface of the shell, equipped with a vehicle wiring TVEL device-to-device output defective fuel elements and control system.

According to the invention the mechanisms pieces of tubing in the size of the shell of a fuel rod for a nuclear reactor VVER-1000 is installed with the possibility of somenew towards each other at a distance, providing a segment of tubing in the size of the shell of a fuel rod for a nuclear reactor VVER-440, movable in the axial direction of the focus control mechanism of the length of the tube-shell of a fuel rod of a nuclear reactor VVER-1000 is provided with a detachable extension cable with a length, providing control of the length of the tube membrane for a fuel rod of a nuclear reactor VVER-440, a calibration mechanism one end of the tube-shell of a fuel rod of a nuclear reactor VVER-1000 is provided with a detachable extension cable with a length for the calibration of one end of the tube-shell of a fuel rod of a nuclear reactor VVER-440 with dosulfiram tube wrapper, mechanism mounting bracket into the grooved end of the tube-shell for a fuel rod of a nuclear reactor VVER-1000 features a removable rod inside the cavity, which follows the contours of the plugs for fuel elements in a nuclear reactor VVER-440, coaxially to the axis of the tube wrapper for TVEL VVER-440, with a bias provided by a window in the piston rod feeder stub orientator the latter, provided with the inlet of the tube-shell for TVEL dimensional reactor VVER-440, and on the other hand detachable extension cable with dosulfiram, equalizer ends of the shells, the Stripping mechanism of the weld and the mechanism of ultrasonic weld inspection after electron-beam welding the caps to the shell is equipped with detachable cords with tosylates membranes for fuel rod poison the aqueous reactor VVER-440 on the position of the aligned ends of the shells, Stripping weld, ultrasonic weld inspection, the mechanism for stacking and feeding shells to TVEL VVER-440 on the equipment is provided with a detachable stem extension length, ensure the contact of the open end of the shell with the column of fuel pellets in the bed is made in the form of a hollow tube placed inside a movable rod mounted at one end in the tool clamp mechanism of feeding, and on the other hand is interacting with its collet, with blank, snaryazhenii shell, cut off the clamps of the end posts of the fuel pellets in the cradle installation wyposarzenia mounted for displacement in the direction of reducing the lengths of the columns of fuel pellets for Fuel rods of a nuclear reactor VVER-440, the cleaning mechanism from dust of the open end of the filled shell and mounting clamps into the open end of the filled shell is provided with a detachable cords with tosylates shell for TVEL VVER-440 on the position of the cleaning and pressing of tabs.

Other differences is that the removable extension is made in the form of a simulator of a fuel rod with length equal to the difference between the length of TVEL VVER-1000 and TVEL VVER-440 fixed coaxially to one end of the rod tosylates made in the form of pneumatic cylinders run on the table styling shells clamps shells in each lodgement.

Running vs the x above distinctive features allows you to use the automatic production line of the fuel rod for a nuclear reactor VVER-1000, and for a nuclear reactor VVER-440 after proper adjustment and installation of the removable elements and Vice versa, to increase the yield of the fuel element for a nuclear reactor VVER-440 by eliminating skew stub when it is press-fit into the shell that the proposed design of the pressing rod. The proposed design allows for the production of Fuel elements on one line, not two (see Automatic line production of fuel elements patent RU 2155395, IPC 7 G 21 C 21/02 from 17.02.1999,, publ. 27.08.2000 year).

However, analogues and the automatic production line of fuel elements - the prototype has a number of disadvantages:

a) there is no device control curb weight of shell and sorting by weight;

b) there is no box in which to spend the removal of the pins and the release of defective curb weight of the shell, since the work with an open uranium requires respiratory protection personnel;

in) in the detection of marriage filled shell on the device control and inspection on the internal components as described in patent 2155395 defective curb shell was sent back for completion.

However, in the description of the patent information on the continuity and length of the column of fuel pellets, the gaps between them, to identify crumbs fuel Mat is Rial between tablets missing. Needed a release filled shell, and the device demilitarization in line patent 2155395 missing;

g) under the patent 2155395 defective pressure under the membrane of the fuel Rods are removed from the line. The device of the demilitarization missing;

(e) patent 2155395 metallographic testing of weld seam of a fuel rod is not held - no device for the production of samples for such control;

(f) patent 2155395 chemical composition of helium under cover of a fuel rod is not analyzed, although it is possible the presence of extraneous helium gaseous impurities which adversely affect the quality of the fuel element.

It is known that the fuel Rods are the most responsible and the most intense structures of the active zone of the nuclear power reactor.

The output of a fuel element failure leads to the most dangerous consequences - hit nuclear fuel and fission products in the coolant circuit.

The materials included in the composition of a fuel rod must be compatible with each other, have good corrosion and erosion resistance, corrosion resistance to fission products, good radiation resistance, i.e. minimally to change their properties, structure and size under the influence of reactor irradiation (see Development, production and operation of fuel cells power the ical reactors, book 1, edited by Fgurative. - M.: Energoatomizdat, 1995, pp. 40, 44).

Helium filling the shell Fuel under pressure, is composed of extraneous gases hydrogen, oxygen, nitrogen, methane, carbon monoxide, and it is possible exceeding of these contaminants above acceptable level, which will adversely affect the quality of a fuel rod, especially when it is operating in the active zone of the nuclear reactor. So the oxygen can increase the oxygen potential of the fuel, which affects the health of the fuel Rods, thus increasing the corrosion of the shell (see ibid., p.63). Hydrogen is highly corrosive to zirconium of the Fuel cladding at temperatures of their operation in consequence of the formation of zirconium hydride.

The shell is subjected to hydrogenation, is embrittled and under the influence of the stresses caused by temperature changes of the fuel rod may break down. The fuel rods lose their tightness (see ibid., p.86, 87).

A similar effect on the shell of zirconium has and methane. Carbon monoxide impairs the efficiency of the fuel Rods (see ibid., p.95).

Zirconium at high temperatures reacts with nitrogen to form nitrides. Dissolved nitrogen increases the electrical resistance, changes the temperature α-β transformation of Zirconia in the same way as oxygen, but to a greater extent (see Metallurgy the Oia zirconium, translation from English under the editorship Gasperson, publishing house of foreign literature. M., 1959, str).

An object of the invention is the expansion of technological capabilities of automatic lines for manufacturing of Fuel elements, improving their quality and yield.

This technical problem is solved in that in the automatic production of Fuel elements for nuclear reactors VVER-1000 and the manufacture of Fuel elements for nuclear reactors VVER-440 with extension containing devices:

- preparation of membranes to the equipment with welding stub to one end;

shell and its weighting;

- equipment of the column of fuel pellets in the open end of the sheath;

- Stripping of the open end of the filled shell;

- mounting clamps into the open end of the filled shell;

control and grading curb shell by the presence of internal components;

- sealing by welding the caps to the open end of the filled shell (further fuel element under the pressure of helium under cover;

control and inspection pressure within the sheath of the fuel element;

- ultrasonic testing of the weld;

- surface treatment of a fuel rod with oxidation;

- vehicle wiring device-to-device output defective curb shells and TVEL and cf is DSTV automation;

according to the invention, after the device mounting clamps into the open end of the filled shell is placed a device weighing loaded shell interlocked with the device weighing shell with a cover that defines “net” weight of nuclear fuel in the form of a column of tablets and equipped vehicle o defective by weight of a loaded shell from the process stream, the control device and grading curb shell internal components equipped with an additional control elements and grading: continuity and length of the column of fuel pellets, the length of the gap between the cover and the tablet, the length of the gap between tablets, the amount of gaps, chips, the volume of a single crumb between tablets, the length of the gap between the last tablet and the retainer, the length of the spring retainer or the total length of the stub pins and the vehicle output defective curb shells from the process stream into a built-in automatic line Boxing, communicated with vehicles o defective by weight of loaded shells, output defective fuel elements from the monitoring device and formation pressure within the fuel cladding and the output of defective fuel elements of the control device of the weld, the ri before built-in automatic line box is placed lodgement for defective curb shell or defective fuel element, equipped with fibresystems its fluctuations demilitarization of the fuel column of tablets in a box, which contains:

- receiving container rasarajani tablets from the open end of the shell after removal of the latch connected to the receiving container flexible tableprovider;

device destructive testing pressure of helium under the fuel cladding and its composition in the form of a test chamber communicated with a vacuum system and is equipped with proclivities of fuel cladding, strain gauge pressure monitor and analyzer for determining the composition of helium;

device metallographic sample preparation quality control of the weld in the form of a cutting machine using scrap shells.

The proposed automatic line allows you to expand its technological capabilities through:

- weight control is loaded in the fuel Rods of nuclear fuel pellets, which is very important for the normal operation of a nuclear reactor and avoid distortion of the neutron and temperature fields in each fuel element;

- expansion volume control of each fuel rod in the gaps, chips, etc.,

- demilitarization of defective curb shells and TVEL;

- determine the composition of helium;

- preparation of metallographic samples under the control of the quality of the weld is not orestano in automatic lines.

In automatic lines will increase the quality of output of the fuel Rods due to the return of the tablets on the re-gear after the release of defective curb shells and TVEL, return shells on re-equipment due to the demilitarization of defective curb shells, return shells on re-equipment TVEL VVER-440 demilitarization shells TVEL VVER-1000, having a greater length than the shell VVER-440, increase control loaded shells of the fuel rod and the Fuel rod and control of gas impurities in helium and its compliance with the standard.

The drawings show the automatic production line of fuel elements and its fragments, where

figure 1 - the Automatic production line of fuel Rods;

figure 2 - Device wyposarzenia;

figure 3 - Detachable cords;

Figure 4 - Box;

5 is a Machine hulls in Boxing;

6 is a destructive Device control pressure in the fuel rod and its composition;

Fig.7. a Device weighing the filled shell;

Fig Device control and inspection on the internal components;

Fig.9 is a schematic diagram of a device puncture and gas analysis.

The automatic production line of the fuel rod for a nuclear reactor VVER-440 automatic lines for manufacturing fuel elements, nuclear reactor VVER-1000 contains:

the device podhotavlyvaet to the equipment, includes an inclined rack and pinion table 1, along which technological sequence posted by mechanisms 2 pieces of tubing with two sides in the size of the shell 3 for a fuel rod with the actuator 4 rotation and axial reciprocation 5, the control mechanism of the length of the tube-shell 3 in the form of rolling a 6 in the axial direction and fixed stops 7 sensor 8, the calibration mechanism shaft 9 at one end of the tube-shell 3 with the actuator 10 axial reciprocating movement adjacent to an inclined table 1 ensuite baths 11, 12, 13 degreasing, rinsing, and drying of the inner and outer surfaces of the tubes the casing 3 adjacent to the baths inclined rack and pinion table 14, along which technological sequence posted by the pressing mechanism 15 plugs 16 in the grooved end of the tube-shell 3 with feeder 17 feed stub 16 to the position of the crimp. The mechanism 18 weighing shell 3, the installation of 19 electron beam weld stub 16 to the shell 3, an inclined rack and pinion table 20, which in the technological sequence placed equalizer 21 the ends of the shell 3, the mechanism 22 cleaning the weld, the mechanism 23 ultrasonic weld inspection and money transactions from mechanism to mechanism on inclined table having a slope of 3-5° with selectors, kickers (not shown) and the roller 24 figure 1);

device 25 wyposarzenia column of fuel pellets in the open end of the shell 3, which includes vibrating feeder 26 supply of fuel pellets 27 on a horizontal cradle 28 in the form of guides in the amount of six pieces for forming pillars of fuel pellets 27, the control device the length of the pillars of fuel pellets with clipper-stop 29 the beginning of the pillars and the cutter-clamp 30 of the end posts of the fuel pellets 27 made of individual cylinders for each post with the spring-loaded rods with elastic material on the end (figure 2), rack and pinion table 31 adjacent to the installation of 25 wyposarzenia with the cradle 32 of six pieces for installation in these shells 3 coaxially to the poles of the open ends in the direction of the fuel columns with stacking mechanism (not shown) and feeding 33 of the shell 3 equipment and removal of filled shells 3, the roller 34 posting shells 3 equipment, tilt table 35 reception filled shells, which in the technological sequence placed;

device 36 cleaning the open end of a filled shell of dust;

device 37 of the mounting clips 38;

device 39 weighing of loaded shells 3;

the conveyor 40;

device control and inspection on the internal components 41, an inclined rack and pinion table 42 receiving interconnect shells 3 coming to the sealing, the roller 43 input curb shell 3 in the device 44 and the output of the fuel element from the device sealing mechanism 45 of the feed stub 46 on the contact-butt welding, an inclined rack and pinion table 47 posted along it

device 48 control and sorting in the pressure inside the fuel rod 3 and

device 49 ultrasonic testing of the weld seam

device 50 surface treatment with oxidizing membrane of a fuel rod 3,

the roller 51 of the transaction to the device 50 of the fuel rod 3, the vehicle wiring from mechanism to mechanism for tilting tables, the output of accepted and rejected TVEL and automation system (not shown) (figure 1).

Mechanisms 2 pieces of tubing in the size of the shell 3 Fuel for VVER-1000 mounted for displacement towards each other at a distance, providing the segment of tubing in the size of the shell 3 of a fuel rod for a nuclear reactor VVER-440.

Movable in the axial direction of the focus 6 of the control mechanism of the length of the tube-shell 3 of a fuel rod of a nuclear reactor VVER-1000 is provided with a detachable extension 52 with a length for the length control of a fuel rod for a nuclear reactor VVER-440 (figure 2).

A calibration mechanism shaft 9 at one end of the tube-shell 3 of a fuel rod of a nuclear reactor VVER-1000 is provided with a detachable extension 53 with the length for the calibration of one end of the tube-shell 3 for TVEL VVER-440 with dosulfiram 54 t the skirts-shell 3. The mechanism 15 fitting plugs 16 in the grooved end of the tube-shell 3 for TVEL VVER-1000 features a removable rod 55 (Fig 3), inside which the cavity 56, which repeats stub for TVEL VVER-440, with a slope of 57 reported through the window 58 in the piston rod feeder 17 caps 16 with the orientator plugs 16, provided with inlet 59 to the tube-shell 3 for TVEL VVER-440 and on the other side of the extension 60 with dosulfiram 61. The equalizer 21 the ends of the shell 3, the mechanism 22 Stripping weld and mechanism 23 ultrasonic weld inspection after electron-beam welding stub 16 to the shell 3 is provided with a detachable extension 62, 63, 64 tosylates 65, 66, 67 shell 3 for TVEL VVER-440 on the position of the aligned ends, Stripping weld ultrasonic testing of the weld (figure 1). The mechanism for stacking and feeding 33 of the shell 3 for TVEL VVER-440 on the equipment is provided with a detachable stem extension 68 with the length for the contact of the open end of the shell 3 with the column of fuel pellets 27 lodgement 28, made in the form of a hollow tube 69 and placed inside a movable rod 70 secured to one end of a collet clamp 33 mechanism of feeding shells 3 equipment and removal curb membranes 3 from the equipment, and on the other hand is interacting with its collet 71 with a plug 16 snaryazhenii shell 3 (Fi is .2).

Cut off the clamps 30 end of the pillars of fuel pellets 27 in the cradle 28 installation wyposarzenia mounted for displacement in the direction of reducing the lengths of the columns of fuel pellets for Fuel of VVER-440 and shown by the solid line and the previous location for the Fuel of VVER-1000 shown by the dashed line. Cleanup mechanisms 36 of the fuel dust the open end of a filled shell 3 and the fitting 37 of the locking tabs 38 into the open end of the filled shell 3 provided with extensions 72, 73 with tosylates 74, 75 shell 3 for TVEL VVER-440 on the position of the cleaning and pressing of tabs.

Removable extension 52, 53, 60, 62, 63, 64, 72, 73 identical among themselves, made in the form of a simulator of a fuel rod with length equal to the difference between the length of TVEL VVER-1000 and TVEL VVER-440 fixed coaxially to one end of the rod tosylates made in the form of pneumatic cylinders 54, 61, 65, 66, 67, 74, 75, identical to each other. On the table 31 of the stacking shells 3 in the cradle 32 is made clamps 76 jackets 3 in the cradle 32.

After the device 37 of the mounting clips 38 posted by device 39 weighing of loaded shells 3 interlocked with the mechanism 18 weighing shell 3 with a plug 16 that defines “net weight” of nuclear fuel in the form of a column of fuel pellets 27 and is provided with a vehicle 77 conclusion rejected by weight of loaded shells 3 of techno is oricheskogo stream.

The device 41 of the control and inspection curb shell 3 on the internal components equipped with an additional control elements and sorting:

- continuity and length of the column of fuel pellets 27;

- the length of the gap between the cap 16 and the tablet 27;

- the length of the gap between the tablets 27;

- the sum of the gaps;

- chipped;

- volume single crumb between tablets 27;

- the length of the gap between the last pill 27And retainer 38;

- the length of the spring retainer 38 or the total length of the stub clamps 38, contains a linear displacement sensor 78, the photosensor of the measurements 79, the photosensor of the end of measurements 80, eddy-current sensor 81, the collimator 82 with two measuring channels on the basis of the source of Co57(cobalt) and equipped with a vehicle 83 conclusion of defective curb membranes 3 from the process stream into a built-in automatic line box 84, communicated with the vehicle 77 conclusion rejected by weight curb membranes 3 from the process stream, with the vehicle 83 conclusion the defective fuel rod 3 from the device 41, the vehicle 85 o defective fuel elements from the device 48 of the control and sorting in the helium pressure inside the fuel rod 3 and the vehicle 86 device 49 ultrasonic weld inspection.

Before the built-in auth is automatic line box 84 posted by lodgement 87 for defective curb shell 3 or defective fuel rod, equipped with fibresystems 88 variability and demilitarization of the fuel pole tablets per box 84, in which it is placed:

- receiving container 89 rasarajani tablets 27 from the open end of the shell 3 after removal of the retainer 38, United flexible tableprovider 90;

device destructive testing pressure of helium under the shell 3 of a fuel rod and its composition in the form of a test chamber 91 provided with a vacuum system 92 and provided with proclivities 93 fuel cladding, strain gauge 94 pressure control and detector 95, determining the composition of helium;

device metallographic sample preparation quality control of the weld in the form of a cutting machine 96.

The automatic production line TVEL VVER-1000 and TVEL VVER-440 operates as follows.

The rod docilely-pneumatic cylinders 54, 61, 66, 67, 74, 75 coaxially fixed detachable cords 52, 53, 60, 62, 63, 64, 72, 73. Mechanism 2 on the rack and pinion table 1 slip and fixed so as to provide cutting tube in the size of the shell 3 for TVEL VVER-440. The mechanism 15 pulling the plugs 16 in the grooved end of the tube-shell install removable rod 55.

In the mechanism of stacking and feeding 33 of the shell 3 for TVEL VVER-440 set the stem extension 68 with the length for the contact of the open end of the shell 3 with the column of fuel that the notches 27 in the lodgement 28, fix one end in the collet clamp 33 mechanism of feeding shell 3 on the equipment.

Cut off the clamps 30 ends of the pillars fuel pellets 27 in the cradle 28 installation 25 wyposarzenia shift in the direction of reducing the lengths of the columns of fuel pellets 27 and is fixed so as to ensure the formation of the pillars of fuel pellets 27 for TVEL VVER-440.

After carrying out the necessary restructuring of the production TVEL VVER-1000 manufacturer TVEL VVER-440 line put into service.

On the inclined rack and pinion table 1 handset supplied to the engine 2 pieces of tubing in the size of the shell 3 for TVEL VVER-440, where with the help of the actuator 4 rotation and axial reciprocating movement of the 5 mechanisms 2 with two sides cut off the tube in the size of the shell 3 for TVEL VVER-440.

After the cutting is the removal mechanisms 2 and the tube-shell by an inclined table 1 comes to the position control of the length of the tube-shell 3, which uses the sensor 8 are given the command to measure the length of the tube-shell 3 between the movable stop 6 with extension 52 and a fixed stop 7. After measurement, the fixed stop 6 together with extension 52 is given to the original position, and the tube-shell 3 or inferred from the line as marriage in length, or as good on the table 1 is moved to the position of the calibration, which uses the actuator 10 of the rod 9 is the caliber of the WHC one end of the tube-shell, and on the other side of the tube-shell 3 is held by the extension 53 with dosulfiram 54. After calibration, the extension 53 with dosulfiram 54 returns to its original position, and the tube wrapper on the table 1 supplied to the bath 11, 12, 13 degreasing, rinsing, and drying of the inner and outer surfaces. After degreasing, rinsing, and drying tube shell 3 on the inclined rack table 14 arrives at the position of the mechanism 15 fitting plugs 16 in its grooved end extension 60 with dosulfiram 61 tube-shell 3 calibrated end shall be expedited to the position of the crimp. From the feeder 17 and the plug 16 is adjudged to be in removable rod 55, the pre-guideline focuses pressing end to the grooved end of the tube-shell 3. Oriented cover 16 through the window 58 enters removable rod 55, the calibrated end of the tube-shell 3 through the opening 59 in the removable rod decalcifies the inclination of 57 in the cavity 56, which follows the contours of the plugs 16 and zapressovyvajutsja calibrated in the end. After weighing mechanism 18 shell with sealed plug (hereinafter shell 3) by an inclined rack table 14 and the roller 24 is supplied to the installation of 19 electron beam welding the caps to the shell, where the sloping rack and pinion table 20 in position 21 align the ends of the shell 3 by using the extension cable 62 with doxylamine is 65, the mechanism 22 Stripping weld stub with the shell using the extension 63 and tosylates 66 and mechanism 23 ultrasonic testing of the weld. Defective shell 3 after ultrasonic weld inspection are displayed with a line, and the fit of the shell 3 by the roller 34 comes to a rack and pinion table 31 adjacent to the installation of 25 wyposarzenia. On rack and pinion table 31 by means of a feeding mechanism 33 and a removable shaft extension 68 in the form of a hollow tube 69, rolling stock 70 in the pipe 69 and a collet clamp 71 shell 3 with its cover is clamped collet 71 shall be expedited and ensures the contact of the open end of the shell with the column of fuel pellets 27.

Snaryajenie shell 3 by the clamping device 76 are fixed in the cradle 32 of six pieces at a time and when running the installation 25 wyposarzenia from the feeder 26 tablets 27 fill the containers 28 to slam-lock 29, which at the time of formation of the pillars is closed. After the containers are filled with tablets work cut off the clamps 30, opens the clipper-the stop 29 and the six pillars of tablets 27 are received in the shell 3, which in the course of their equipment after the opening of the clamp 76 are inclined rack table 35 unit 36 cleaning the open end of a filled shell 3 from the fuel dust, where with the help of the extension 72 and tosylates shell shall be expedited to the mechanism 36 cleaning and presented with clean, and then arrives at the device 37 of the mounting clips 38 using the extension 73 with dosulfiram 75. After fitting clamps curb shell is supplied to the device 39 weighing and conveyor 40 to the device 41 of the control and inspection on the internal components.

Defective curb the shell internal components are sent back for completion, and suitable equipped shell by an inclined rack table 42 - the drive roller 43 input device 44 of the sealing and output of the fuel rod from the device 44 of the seal. The device 44 of the sealing plugs 46 are received in the welding zone of the mechanism 45 of the feed stub and is contact-butt welding stub 46 to the shell 3 under the pressure of the inert gas under the shell. The same roller 43 is sealed curb shell (hereafter FE) arrives at an inclined rack and pinion table 47, which is used for the control and classification of TVEL pressure within the shell on the device 48 and the control and classification of TVEL on the device 49 ultrasonic weld inspection.

Defective fuel Rods are removed from the line, and suitable for roller 51 comes to the installation of 50 surface treatment with oxidizing membrane of a fuel rod 3.

After weighing the filled shell 3 on the device 39 according to the difference of the weights of the empty shell is his 3, weighted on the mechanism 18, is determined by the “net weight” of the nuclear fuel pellets 27 in each fuel element.

Curb shell 3 without deviation weight follow the process flow stream, and the deviation of the weight of the vehicle 77 in Boxing 84, where the weight of nuclear fuel pellets 27 is brought to the required standards, or subjected to a release.

Curb shell 3 without rejecting the weight of nuclear fuel pellets 27 are received in the device 41 of the control and inspection where moving through the sensor linear position 78, the photosensor 79 the start of the measurement, the photosensor 80 end measurements, eddy-current sensor 81 and the collimator 82 with two measuring channels are checked and sorting:

- continuity and length of the column of fuel pellets 27;

- the length of the gap between the cap 16 and the tablet 27;

- the length of the gap between the tablets 27;

- the sum of the gaps;

- chipped;

- volume single crumb between tablets 27;

- the length of the gap between the last pill 27 and the latch 38;

- the length of the spring retainer 38 or the total length of the stub clamps 38.

Good curb shell 3 is moved by the technological flow of the sealing device 44, and defective curb shell 3 vehicle 83 built-in automatic line Boxing 84.

In Boxing 84 defective ammunition is installed shell 3 when the device 41 is subjected to release preliminary removal of the retainer 38.

Vehicle 85 defective fuel rod from the device 48 of the control and sorting in the pressure of helium inside the shell 3 of a fuel rod comes in a box 84, where it is subject to control measurement of the pressure of helium - destructive control.

The end of a fuel rod is placed in a test chamber 91, which vacuumized through the vacuum system 92 to 30 mm Hg, proclivities 93 shell 3 of a fuel rod is pierced and is determined by the helium pressure strain gauge 94.

If the pressure is the same pressure that is defined in the device 48, then make a conclusion about the suitability of the device 48 and existing defect in the shell 3 of a fuel rod, through which the leaking helium.

At the same time helium analyze the content of hydrogen, oxygen, nitrogen, methane and carbon monoxide gas analyzer 95.

In the case of non-compliance with helium GOST, i.e. at the excess content in helium gases listed above required limits, then stop the operation of the sealing device 44 and replace the balloon with helium, used for the sealing of a fuel rod to create pressure under the shell 3 of the fuel element.

Vehicle 86 device 49 ultrasonic inspection of defective fuel Rods go in the box 84. From the shell of a fuel rod with the cutting machine 96 in Boxing 84 cut the tissue samples for metallographic weld inspection.

The release is dressed shells 3 is performed on the lodgement 87 using VibroSystM 88, when the oscillation which pillar tablets 27 by a flexible tallapragada 90, connecting the open end of the filled shell 3 with the receiving container 89, delivered to the receiving container 89.

As the filling of the receiving container 89 with tablets 27 is sent to the device equipment 25, where the tablets 27 after the input control reused.

Shell after demilitarization Fuel of VVER-1000 are cut in the size of the shell TVEL VVER-440 and reused.

Thus was created the automatic production line TVEL, fully meet the modern requirements of the fuel element.

The automatic production line of fuel elements for a nuclear reactor VVER-1000 nuclear reactor VVER-440 with extension containing devices:

- preparation of membranes to the equipment with welding stub to one end of the shell and its weighting;

- equipment of the column of fuel pellets in the open end of the sheath;

- Stripping of the open end of the filled shell;

- mounting clamps into the open end of the filled shell;

control and grading curb shell internal components;

- sealing by welding stub to curb the shell (in the future, fuel cell) under the pressure of the inert gas helium under the shell;

control and inspection pressure within the sheath of the fuel element;

- ultrasonic testing of the weld;

- surface treatment with oxidizing membrane Fuel, vehicle wiring device-to-device output defective curb membranes and fuel cells and automation equipment, characterized in that after the device mounting clamps into the open end of the filled shell is placed a device weighing loaded shell interlocked with the device weighing shell with a cover that defines "net" weight of nuclear fuel in the form of a column of tablets, and is equipped vehicle o defective by weight of a loaded shell from the process stream, the control device and grading curb shell internal components equipped with an additional control elements and sorting in the continuity and length of post fuel pellets, the length of the gap between the cover and the tablet, the length of the gap between the tablets, the amount of gaps, chips, the volume of a single crumb between tablets, the length of the gap between the last pill and the retainer, the length of the spring retainer or the total length of the stub pins and the vehicle output defective curb shells from the process stream into a built-in auth is automatic line Boxing, communicated with vehicles o defective by weight of loaded shells, output defective fuel elements from the monitoring device and formation pressure within the fuel cladding and the output of defective fuel elements of the control device of the weld, because the built-in automatic line box is placed lodgement for defective curb shell or defective fuel element with fibresystems its fluctuations demilitarization of the fuel column of tablets in a box, which contains:

- receiving container rasarajani tablets from the open end of the shell after removal of the latch is connected to the receiving container flexible tableprovider;

device destructive testing pressure of helium under the fuel cladding and its composition in the form of a test chamber communicated with a vacuum system and is equipped with proclivities of fuel cladding, strain gauge pressure monitor and analyzer for determining the composition of helium;

device metallographic sample preparation quality control of the weld in the form of a cutting machine using scrap shells.



 

Same patents:

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: 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

The invention relates to nuclear energy, in particular for fuel Rods for the fuel cartridges of nuclear RBMK-type reactor consisting of two fuel assemblies (FA), and can be used in Fuel elements and other assemblies, in which it is necessary to reduce a local burst of neutrons, causing increased energy

The invention relates to structures steam-generating power plants high calorific and, first of all, can be used in steam generating plants nuclear fuel (steam-water nuclear reactors)

The invention relates to nuclear energy, in particular to fuel design for a composite tape system power control active zone (SMT) power reactor type VVER-440

The invention relates to the development of vented fuel elements, their experimental development in nuclear reactors, in particular thermionic fuel elements, while creating electricity generating channels thermionic reactor Converter

The invention relates to the nuclear industry, namely, creating and experimental handling of fuel elements for nuclear reactors
The invention relates to nuclear energy, namely technological ways of protecting the items in the active zones of nuclear reactors channel and frame type from destruction, and can be used to suppress the debris effect, fretting and local corrosion of the fuel elements (FE), fuel assemblies (FA), technological channels (TC)

The invention relates to the technology for the production of sintered ceramic fuel pellets for a nuclear reactor containing the fissile material

FIELD: nuclear industry.

SUBSTANCE: proposed method is used for manufacturing fuel elements of type VVER-1000 and VVER-440 reactors when sealing them in resistance butt welding machine using expanding chuck. Novelty is that spent chucks cleaned from uranium dioxide are used as charge to be melted for producing new ones of sufficient strength and flexibility. Spent chucks are melted at 1300 - 1350°C for 20 - 25 min., melt is degassed at pressure of 4.5 x 10-3 of mercury; when cleaning molten bronze from nonmetallic admixtures, the latter are upset on cooled crucible walls in the course of short-time disconnection and connection of inductor load; ingots obtained are hardened in water at 780 ±10°C and annealed at 320 - 340 °C for 3 - 3.5 h to make them flexible; then expanding chucks are manufactured by mechanical method.

EFFECT: provision for using spent chucks to produce new ones.

2 cl, 2 dwg

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

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.

1 dwg

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: 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

Up!