RU2455715C1 - Device for transferring covers with spent nuclear fuel - Google Patents

Abstract

FIELD: power industry.

SUBSTANCE: device for transferring covers with spent nuclear fuel includes gripping device, lifting winch blocks, and cable drums installed on the flooring. Gripping device is suspended on two independent ropes on twin pulley blocks inside protective chamber. Protective housing is installed in through hole of the roofing; a groove is made in upper end face of protective housing, into which protective plate is installed, with possibility of regulating its position. Gaps between protective housing and protective plate are filled with biological protection. Lifting winch blocks are installed on protective plate and consist of three groups of pair blocks.

EFFECT: invention allows improving the reliability and radiation safety of operation when transferring the covers with spent nuclear fuel.

7 cl, 6 dwg

Description

The invention relates to the field of nuclear energy, to the main technological equipment for transport and technological operations for the treatment of radioactive waste and spent nuclear fuel, in particular to devices for reloading covers with spent nuclear fuel.

The following requirements are required for radioactive waste and spent nuclear fuel management equipment:

- all operations are carried out in a specially equipped protective chamber.

- special lifting devices are used that exclude spontaneous disengagement with products containing spent nuclear fuel.

A known system for reloading and preserving nuclear fuel, which includes: an intermediate box with a conveyor device, vertical channels, sealing means. The moving channel is designed to transfer fuel assemblies from the transport container of the reactor compartment to the protective chamber. The protective chamber serves to connect the channel for movement with the shielded camera and contains devices for sealing the channel for movement, connection with the containers of the conveyor device, removal and re-installation of covers from the containers. The conveyor device contains waterproof containers with lids designed for installation of fuel assemblies and reflective elements in them. The conveyor device moves containers with fuel assemblies installed in them between the moving channel and the transport channel. Through the transport channel, containers with fuel assemblies installed in them are moved to the storage area.

(UK patent No. 2023911, IPC G21C 17/06; G21C 19/06; G21C 19/32, published 03/01/1980).

The protective chamber contains a large number of mechanisms that ensure the operation of the system, access to which is difficult, which leads to a decrease in reliability and maintainability.

A device is known for lowering and raising fuel elements, including a gripper suspended on blocks located in a protective chamber for loading and unloading fuel assemblies in a transport container (WO 2009135900, IPC G21C 19/32, published 12.11.2009).

A device is known for reloading capsules with spent nuclear fuel, comprising a transport pipe for reloading the capsules, a cargo rope of a crane mechanism with a gripper fixed to it. In order to prevent the capsule from falling during the breakage of the cargo rope of the crane mechanism or during emergency opening of the gripper, the transport pipe is equipped with a movable support equipped with folding two-arm levers that overlap the central opening of the support and interacting with the capsule and walls of the transport pipe, the cylindrical surface of which becomes conical and the movable support flexible connections through a system of fixed and moving blocks, each of which is equipped with a spring, a drum equipped with a brake, and rotary balances are connected to the brake engagement mechanism, equipped with a spring, and the springs can interact with limit switches with increasing effort in flexible connections, and the mass of the balances is greater than the mass of the movable support (AS No. 1235387, IPC G21C 19/32, priority 06.09.1984 )

A device for loading spent fuel assemblies is known, including a radiation shielding unit, a lifting mechanism, a guiding device with a receiving funnel located above the cutting chamber for spent fuel assemblies, in which there is a storage container for spent fuel assemblies. The radiation protection unit is equipped with grippers for joining them from the spent fuel assemblies and loading them into the container of the railway platform.

(RF patent No. 2094863, IPC G21C 19/00, published 1997.10.27).

The disadvantage of these devices is that they do not provide sufficient biological protection, since it is possible to get spent nuclear fuel from the package into the external environment.

A device is known for reloading a capsule with spent nuclear fuel, comprising a transport pipe intended for reloading the capsule, a cargo rope of a crane mechanism with a grip fixed to it, and a mechanism for holding the capsule from falling, the latter including a grip interacting with the capsule by means of a sling device mounted on the end the surface of the capsule, and through a system of flexible connections, is connected to the brake engagement mechanism, interacting with the limit switches of the crane Khanism. (RF patent No. 2066488, IPC G21C 19/00, G21C 19/32, published September 10, 1996).

The disadvantage of this device is that it is designed to transfer capsules into a single container, so it cannot be used to transfer capsules with spent nuclear fuel into a multi-seat container.

A device is known for handling spent nuclear fuel in a protective chamber in the form of a crane containing a gripper, load lifting mechanisms, a gripping control mechanism, and two independent cargo ropes passing through two guide blocks mounted at an angle one above the other are used to move the cargo gripper on a freight trolley, while the line of intersection of the planes passing through the centers of the grooves of the blocks coincides with the vertical axis of the capture with the possibility of eliminating the displacement of the center of mass of the cargo when in the break of one of the cargo ropes, on the cargo trolley are placed the guide blocks of the ropes of the main and emergency mechanisms for moving and controlling the gripper and the drive for moving the trolley, the cable drums of the main and emergency drives for moving and controlling the gripper, mounted stationary, for example, on opposite sides inside the protective chamber, in motion with the help of shafts passing through the mortgages installed in the ceiling of the protective chamber, and drives located outside the protective chamber at “h In the open "premises, the controlled cargo grab is suspended on a block suspension made in the form of a frame, on the axes of which are mounted rocker arms with blocks for two main power ropes (RF Patent No. 2352516, IPC B66C 17/00, published on 04/20/2009).

The disadvantage of this device is the lack of biological protection, most of the mechanisms are in the protective chamber, which makes it difficult to access for equipment maintenance.

The technical task of the invention is to increase the reliability and radiation safety of work for overloading covers with spent nuclear fuel.

The problem is solved due to the fact that in the device for reloading covers with spent nuclear fuel, containing a gripper suspended on two independent ropes on double blocks inside the protective chamber, hoist winch blocks, cable drums installed stationary on the ceiling, in the through hole of the ceiling a protective case is installed, a recess is made at the upper end of the protective case, into which a protective plate is installed, with the possibility of regulating its position, the gaps between the protective body ohm and the protective plate are filled with biological protection, the lifting winch units are mounted on a protective plate and are composed of three groups of paired blocks.

In addition, three groups of paired blocks include paired leveling blocks located one above the other whose axes are oriented at an angle to each other, paired deflecting guide blocks whose axes are angled to each other, and paired coaxial guide blocks.

In addition, to adjust the position of the protective plate in two perpendicular horizontal directions manually, adjustment screws are installed symmetrically on the sides of each of its sides. In addition, lead shots are scattered in the gaps between the protective casing and the protective plate as biological protection.

In addition, to prevent skewing of the protective plate during operation, clamps are installed on both sides of the plate.

In addition, openings are made in the protective plate for the passage of two independent cargo ropes, in order to reduce the diameters of the holes in order to reduce the radioactive effect, the streams of expansion blocks, guide blocks and streams of gripping device blocks located underneath are successively connected by independent ropes.

In addition, in the uppermost position, the gripper is located in the through hole of the protective housing.

The invention is illustrated by drawings.

Figure 1 - General view of a device for reloading covers with spent nuclear fuel.

Figure 2 is a General view of a device for reloading covers with spent nuclear fuel in plan.

Figure 3 - the location of the blocks on the protective plate of the device for reloading covers with spent nuclear fuel.

4 is a protective plate with a gripping device located below it.

5 is a block diagram of the gripper device.

6 is a diagram of the storage of freight ropes.

The device for reloading the covers with spent nuclear fuel includes a protective housing 2 installed in the through hole of the floor 1, which is designed to protect against radiation, below the floor 1 there is a protective chamber 3 of the package of covers, at the upper end of the protective body 2 there is a recess in which is installed protective plate 4, on which there are three groups of paired blocks of a lifting winch with built-in sensors (not indicated in Fig.), including paired equalizing blocks 5, located one above the other, the axis otorrhea oriented at an angle relative to each other and on both sides of the compensating units 5 are paired deflecting guide blocks 6, the axes of which are arranged at an angle to each other on the same level in height, and paired coaxial guide blocks 7.

On the overlap 1 of the chamber 3 complete sets of covers on one side of the protective plate 4 are cable drums 8 and 9, mounted stationary on the frames 10 and 11, located at different levels in height.

On the floor 1, the main gearboxes 12 of the displacement drives are located with a gripping device 13 located in the protective chamber 3 of the cover assembly, mounted on the block suspension 14 in the form of a frame with dual blocks 15 mounted on it, suspended on two independent cargo ropes 16 and 17. The gripping device 13 equipped with a control system with microswitches (not shown in Fig.).

The cable drums 8 and 9 are made with right and left thread for winding on each two branches of the cargo ropes 16 and 17. And are equipped with position sensors of the gripping device (not shown in Fig.).

The location of the guide blocks 6 at an angle to each other is caused by the need to withstand the permissible deflection angle of the ropes 16 and 17 on the reels 8 and 9, and the characteristics of the ropes: the minimum tension force, the deflection angle of the rope, the number of turns, the profile of the streams are determined by calculation. The drums at the edges should have borders on both sides to prevent the ropes from falling off the drum.

The scheme of the storage of cargo ropes is shown in Fig.6.

A rope 16 extending from the drum 8, enveloping the deflecting guide block 6 sequentially from above, then from the bottom of the gripper unit 15, from above the upper leveling block 5, from below the block 15 located diagonally to the previous block 15 of the gripper, the guide block 7 from above is mounted on drum 9. Rope 17, coming from drum 8, enveloping sequentially from above the deflecting guide block 6, then from below the block 15 of the gripper, from above the lower leveling block 5, from below the block 15, located diagonally to the previous block 15 of the gripper, on top of the guide block 7, is mounted on the drum 9.

In this case, streams connected in series by independent ropes 16 and ropes 17 of equalizing blocks 5, guide blocks 6, guide blocks 7 and streams of blocks 15 of the gripping device 13 located under them are made matching.

For the passage of the cargo ropes 16 and 17, holes 18 are made in the protective plate 4, and the coincident streams of the blocks make it possible to reduce the diameter of these holes and thereby reduce the radioactive effect.

In the uppermost position, the gripper 13 is located in the through hole of the protective housing 2.

The protective plate 4 is installed in the recess of the protective housing 2 with the possibility of adjusting its position for precise guidance of the gripping device 13 to the fungus 19 of the case with spent nuclear fuel, the guidance is carried out manually in two perpendicular horizontal directions using the adjusting screws 20 located on each side of the protective plate 4 symmetrically to its lateral sides, the gaps between the protective housing 2 and the protective plate 4 are filled with biological protection, for example, in the form of lead shot 21.

To prevent skewing of the plate during operation, clamps 22 are installed on two opposite sides of the plate.

The device operates as follows.

The control system opens the gripping device 13. At the same time, the microswitch is activated on the gripping device control drive, which sends a signal to the operator panel “capture is open”. Using the cargo ropes 16 and 17, unwinding from the cable drums 8 and 9, the gripper 13 is lowered.

When a certain distance is reached to the fungus of the case, a signal at a position sensor of the gripping device switches to low speed. The grip is lowered onto the fungus of the case placed in the transport container.

When the "slack" of the cargo ropes 16 and 17 appears according to the signals of the sensors built into the blocks, the drive for moving the gripper is turned off and the rotation of the cable reels 8 and 9 is turned off. At the same time, the microswitch on the grip control drive is activated, which sends a signal to the operator console “grip is closed”.

The grip with the case rises. When the cover is raised to a predetermined height by the signal of the position sensor of the gripping device, the displacement drive is switched off.

A technological trolley is fed under the cover (not shown in FIG.). The gripping device 13 with a cover is lowered onto the trolley. When there is a “slack” of the cargo ropes according to the signals of the sensors, the drive for moving the gripper is switched off. The control system opens the grip. At the same time, the microswitch on the control drive is triggered, which sends a signal to the operator panel "capture is open."

Capture rises to a predetermined height. Using technological means of the protective chamber, spent fuel is removed from the case. Installation of the cover in the transport container occurs in the reverse order.

The kinematic scheme of storage provides synchronous rotation of the drums in one direction, while the branches of the ropes 16 and the branches of the ropes 17 are connected with different drums, but due to their rotation in one direction, all the branches of the ropes are moved in one direction.

This design solution eliminates the skew and turn of the grip during operation, ensures vertical lifting of the load and the uniform distribution of loads on the cable drums.

Claims (7)

1. A device for reloading covers with spent nuclear fuel, containing a gripping device suspended on two independent ropes on twin blocks inside the protective chamber, hoist winch blocks, cable drums mounted permanently on the floor, characterized in that a protective body is installed in the through hole of the floor , at the upper end of the protective housing there is a recess in which the protective plate is installed, with the possibility of adjusting its position, the gaps between the protective housing and the protective plate ying biological protection hoisting winch units are mounted on a protective plate and are composed of three groups of paired blocks. 2. The device for reloading covers with spent nuclear fuel according to claim 1, characterized in that the three groups of paired blocks include paired equalizing blocks located one above the other, whose axes are oriented at an angle to each other, paired deflecting guide blocks, axes which are located at an angle to each other, and paired coaxial guide blocks. 3. The device for reloading covers with spent nuclear fuel according to claim 1, characterized in that for adjusting the position of the protective plate in two perpendicular horizontal directions manually, adjusting screws are installed symmetrically on the sides of each side. 4. The device for reloading covers with spent nuclear fuel according to claim 1, characterized in that as a biological protection, lead shot is filled in the gaps between the protective casing and the protective plate. 5. The device for reloading covers with spent nuclear fuel according to claim 1, characterized in that to prevent skewing of the protective plate during operation, clamps are installed on both sides of the plate. 6. The device for reloading covers with spent nuclear fuel according to claim 1, characterized in that the protective plate has openings for the passage of two independent cargo ropes, to reduce the diameters of the holes in order to reduce the radioactive impact, streams connected in series by independent ropes of leveling blocks guiding blocks and streams of gripping device blocks located below them are made matching. 7. The device for reloading covers with spent nuclear fuel according to claim 1, characterized in that in the extreme upper location the gripping device is located in the through hole of the protective housing.

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