RU199747U1 - DEVICE FOR REFLOADING CLUSTERS OF BURN-OUT ABSORBER RODS OR ABSORBING RODS OF THE CONTROL AND PROTECTION SYSTEM AND HEAT-GENERATING ASSEMBLIES OF A NUCLEAR REACTOR - Google Patents

Abstract

The utility model refers to a device for reloading burnable absorber rods (SVP) or absorbing rods of a control and protection system (CPS PS), and fuel assemblies (FA) of a nuclear reactor refers to equipment used during refueling operations at nuclear power plants. The design of the bar of the reloading machine is provided with a double gripping mechanism - external and internal, of which the external gripping mechanism is intended for coupling with the fuel assembly, and the internal one - for coupling with the SVP or PS CPS clusters. The internal gripping mechanism of the rotary telescopic bar of the reloading device is represented by a rigid rod, movable in the vertical direction, on the lower part of which a gripping mechanism is fixed for connection with a gripping element for SVP or PS CPS clusters, and the external gripping mechanism is fixed on the end of the body of the rotary telescopic bar. Moreover, both gripping mechanisms are made in the form of tips with a bayonet connection, and the rigid rod of the internal gripping mechanism is kinematically connected to the drives of the telescopic rod. In addition, the heads of the replaceable gripping elements for the SVP or CPS PS clusters are made in response to the bayonet connection of the rigid rod tip. The technical result is to increase the safety of refueling processes for NPP personnel and reduce the refueling time, and increase the utilization factor of the installed power of the reactor plant. 2 ill.

Description

The device declared as a useful model for reloading the rods of a burnable absorber (SVP) or absorbing rods of the control and protection system (CPS PS), and fuel assemblies (FA) of a nuclear reactor belongs to the equipment used for refueling operations at nuclear power plants.

Bundles of rods of a burnable absorber (SVP) and absorbing rods of a control and protection system (CPS), united by means of traverses having a similar design, are called clusters. The similarity of the traverses makes it possible to perform clutch-uncoupling operations when moving clusters of a TDS or CPS PS using the same gripper.

A device for reloading fuel assemblies of a nuclear reactor is known, containing a guide tube moving on a movable platform with a telescopic rod with a gripper installed in it, movable by a cable drive and having the ability to only axially move relative to the drive housing with a drum (RF Patent No. 2086013 in class G21C 19 / 10 for invention, published on July 27, 1997).

A device for reloading spent fuel assemblies is known, containing a movable platform with a chassis installed above the receiving pool, a lifting device located on a movable platform, a gripper for a spent fuel assembly attached to a lifting device, a protective cup attached to a movable platform having an open from the pool side a cavity for accommodating a part of a spent fuel assembly, the lower edge of the protective cup is located below the water level of the receiving basin, and the grip is installed in the cavity of the protective cup with the possibility of vertical movement (Description to USSR inventor's certificate No. 1572304, G21C 19/10).

The disadvantage of the known devices is the possibility of using gripping elements only for reloading fuel assemblies, and for reloading clusters of the TDS and / or CPS PS, it is necessary to re-equip the reloading device bar.

It is also known a device for reloading a nuclear reactor, which includes a reloading mechanism with a gripper, the body of which by means of a flexible rod is placed in a guide column, moved by a cart with a winch, and replaceable gripping elements - heads for reloadable fuel assemblies or clusters of SVP or PS CPS. (Description to the USSR patent No. 634696, published on November 26, 1078). Replaceable gripping elements are placed in nests, which are movably installed by means of a special drive on the horizontal rails of the frame, attached to the lower end of the guide column. The replaceable gripping elements are equipped with docking units with locking elements in the form of a locking sleeve interacting with a spring-loaded rod with a docking tip located in the guide column of the gripping device body. The docking tip of the gripper body is equipped with a gripping element control mechanism.

The presence of a frame with movable slots for accommodating replaceable gripping elements, fixed in the lower part of the guide column, complicates the process of guiding the refueling mechanism to the reactor service area. Another disadvantage of the device is the complex control system of the docking units, which reduces the reliability of the device and complicates the process of replacing the gripping elements in case of damage.

The closest device to the device for reloading clusters of CPS or CPS and fuel assemblies of a nuclear reactor, which is claimed as a useful model, is a manipulator placed on a trolley for reloading fuel assemblies and clusters of CPS PS of a nuclear reactor, including a drive mechanism for moving the lifting mechanism in the form of a guide tube with an installed in it, a telescopic rod with a double gripping mechanism located in the body with the ability to move in the vertical direction, and a means for controlling and selecting a gripping mechanism, which is made in the form of a cable-operated lever acting on one of the gripping mechanisms, while the other gripping mechanism is disabled, and in the middle position of the lever, both gripping mechanisms are disabled. (Description to the USSR patent No. 677687 in class G21C 19/10, published on July 30, 1979) The double gripping mechanism contains gripping elements interacting, respectively, with the heads of fuel assemblies or cluster heads of the CPS PS and is characterized by fastening the gripping elements on flexible traction elements, determining the need for maintenance of the device by personnel when changing gripping elements, carried out manually.

The disadvantage of the device is the need to use personnel when replacing gripping mechanisms that have been damaged in the event of emergency situations (for example, in case of damage to the surfaces of contacting parts due to deposits and contaminants in the boric acid solution of the cooling pool). The manual replacement of faulty gripping elements in the known transfer device reduces the safety level of the transfer process for personnel. In addition, according to the existing reloading technologies, gripping mechanisms for reloading fuel assemblies and clusters of the SVP and PS of the CPS are a replaceable tool of the reloading device and are stored in the container compartment of the spent fuel pool, therefore all operations to replace replaceable gripping elements on the known reloading device will require lowering the level of the water environment in the compartment. the spent fuel pool in which they are located, which will cause an increase in the time of refueling processes and will lead to a decrease in the installed capacity utilization factor (ICUF) of the reactor plant.

The task to be solved when creating the proposed device for reloading clusters of SVP or PS CPS and fuel assemblies of a nuclear reactor is to mechanize the processes of replacing faulty gripping elements for clusters of SVP and PS CPS with serviceable ones located in the container compartment of the spent fuel pool.

The technical result of using the proposed device is to increase the safety of nuclear reactor refueling processes for NPP personnel, reduce the refueling time, and, as a consequence, increase the ICUF of the reactor plant.

The problem is solved by the fact that in a device for reloading clusters of SVP or PS CPS and fuel assemblies of a nuclear reactor, containing a manipulator placed on a trolley with a drive mechanism and a lifting device including a rotary telescopic rod with a double gripping mechanism located in its body with the ability to move in the vertical direction , external and internal, of which the external gripping mechanism is designed for engagement with the fuel assembly, and the internal one - for adhesion to the clusters of the SVP or PS of the CPS, according to the utility model, the internal gripping mechanism of the rotary telescopic bar of the reloading device is represented by a rigid rod movable in the vertical direction, on the lower part of which a gripping mechanism is fixed for connection with a gripping element for SVP or PS CPS clusters, and the external gripping mechanism is fixed on the end of the body of the rotary telescopic rod, while both gripping mechanisms are made in the form of tips with a bayonet connection, and the rigid rod of the internal gripping mechanism is kinematically connected to the drives of the telescopic rod, in addition, the heads of the replaceable gripping elements for the SVP or PS CPS clusters are made in response to the bayonet connection of the rigid rod tip.

Thus, the mechanization of the processes of changing the grippers of the CPS PS clusters is provided by:

- changes in the design of the rotary telescopic rod due to the implementation of the internal gripping mechanism in the form of a rigid rod with a gripping mechanism for connection with the gripping element of the SVP and PS CPS clusters, made in the form of a tip with a bayonet connection;

- placement of the external gripping mechanism for fuel assemblies at the end of the body of the rotary telescopic rod and making it in the form of a tip with a bayonet connection;

- use of drives of the rotary telescopic bar as a drive for the internal gripping mechanism;

- changes in the design of replaceable gripping elements used during overloading for clusters of SVP or PS CPS due to the new design of their heads, made in response to the bayonet connection of the tip of the rigid rod.

The implementation of the internal gripping mechanism of the rotary telescopic bar of the reloading device in the form of a rigid rod with a tip with a bayonet connection makes it possible to mechanize the procedure for replacing the grippers of the SVP and PS CPS clusters without lowering the level of the aqueous medium in the holding pool compartment. Mechanization of the process of replacing gripping elements for clusters of SVP and PS of the CPS, provided by the implementation of the internal gripping mechanism of the reloading device bar in the form of a rigid rod with a tip with a bayonet connection, allows replacing the faulty gripper of the clusters of SVP and PS of the CPS without the involvement of maintenance personnel and allows the latter to be serviced in the pool holding and outside, which reduces the time of auxiliary operations in the process of refueling the reactor plant. At the same time, supplying the internal gripping mechanism of the reloading device with a tip with a bayonet connection made in the form of a rigid rod in the form of a rigid rod in the form of a tip with a bayonet connection makes it possible to use the drives of the telescopic rod of the reloading device in reloading procedures Fuel assemblies and clusters of SVP or PS of CPS, as well as when changing gripping elements for clusters of SVP or PS of CPS, if necessary.

An example of the implementation of the proposed device for reloading fuel assemblies and clusters of SVP or PS CPS of a nuclear reactor is illustrated by drawings.

FIG. Figure 1 shows a device for reloading fuel rods and clusters of a CPS or CPS PS of a nuclear reactor.

FIG. 2 shows the lower part of the reloading device bar (in section) in the process of replacing faulty gripping elements of the SVP clusters or CPS PS.

A device for reloading fuel rods and clusters of a CPS or SVP of a nuclear reactor (in Fig. 1) includes a bogie 1 with a displacement drive 2 and a reloading mechanism 3, located above the holding pool 4, in which, in the accessibility of the reloading device, in particular, in the container compartment, on the container with the tool (not shown in the drawing) there is a bench device 5 with sockets 6 for placing replaceable gripping elements 7 for clusters of SVP or PS CPS. The rotary telescopic rod 8 of the overload mechanism (the rod rotation drive is not shown) includes a tip 9 fixed in its lower part with a bayonet connection 10 (Fig. 2), intended for engagement with the fuel assembly head (not shown in the drawing), and located along the axis of the rod 8 with the ability to move vertically a rigid rod 11 (connection of a drive for moving a rigid rod with a drive for moving and rotating the rod is not shown) with a tip 12 fixed at its end with a bayonet connection in the form of slots 13. Replaceable gripping elements 7 for SVP or PS CPS clusters, with heads 14, provided with pins 15, are made to match grooves 13 of the bayonet connection of the tip 12, and are placed in the slots 6 (in Fig. 1 and Fig. 2) of the bench device 5, while one of the slots of the bench device remains free.

When servicing the reactor plant during refueling and, if necessary, replacing a faulty gripping element 7 for a SVP or CPS PS cluster, the transfer device 1 is guided by the displacement drive 2 onto the bench device 5 located in the container compartment of the spent fuel pool 3 with slots 6, one of which is free, and in others, gripping elements 7 are installed. The bar 8 of the reloading device with the tip 12 is guided to the coordinates of one of the free sockets 6 of the bench device 5 and when the rigid rod 11 is lowered, the faulty gripping element 7 is installed and fixed in the bench device 5. When the bar 8 is turned, it is released a rigid rod with a faulty gripping element 7 by removing the pins 15 from the grooves 13 of the bayonet connection of the tip 12. By subsequent movement of the reloading device, the rotary telescopic rod 8 is guided to the coordinates of a serviceable gripping device installed in the bench device element 7, the tip 12 of the rigid rod is lowered onto the head 14 of the gripping element 7 and when the rod is turned, the pins 15 are inserted into the grooves 13 of the bayonet connection of the tip 12 of the rigid rod. When the rigid rod 11 is lifted, the gripping element 7 is removed from the seat 6 and placed in the rod cavity.

The reloading device is guided by the displacement drive 2 to the reactor vessel connector (not shown in the drawing), where operations are carried out to extract the fuel assemblies, in which a rod with a tip 9 with a bayonet connection 10 is used, or an overloading of a SVP cluster or a CPS PS using a rigid rod 11 with a tip 12 connected to the gripping element 7.

Mechanization of the processes of replacing faulty gripping elements for clusters of a CPS or CPS, carried out during their remote replacement, provides an increase in the safety of refueling processes for NPP personnel, a reduction in the refueling time and an increase in the ICUF of the reactor installation.

Claims (1)

A device for reloading clusters of rods of burnable absorbers or absorbing rods of the control and protection system and fuel assemblies of a nuclear reactor, containing a reloading device with a drive mechanism and a lifting device, including a telescopic rod equipped with rotary and lifting drives with a double rod located in its body with the ability to move in the vertical direction a gripping mechanism, the outer one of which is intended for engaging with the fuel assembly, and the inner one for engaging with a gripping element for a cluster of rods of a burnable absorber or absorbing rods of a nuclear reactor control and protection system, characterized in that the internal gripping mechanism of the rotary telescopic rod of the reloading device is movable in the vertical direction by a rigid rod, on the lower part of which a gripping mechanism is fixed for connection with a gripping element for the burnable absorber rod clusters i or absorbing rods of the control and protection system of a nuclear reactor, and the external gripping mechanism is fixed to the end of the body of the rotary telescopic rod, while both gripping mechanisms are made in the form of tips with a bayonet connection, and the rigid rod of the internal gripping mechanism is kinematically connected to the drives of the telescopic rod, except In addition, the heads of the replaceable gripping elements for the clusters of the rods of the burnable absorber or the absorbing rods of the control and protection system of the nuclear reactor are made in response to the bayonet connection of the rigid thrust tip of the internal gripping mechanism.

Images