RU2162U1 - RECEPTION DEVICE FOR SPENT NUCLEAR FUEL - Google Patents

Abstract

1. A receiver for spent nuclear fuel containing a pencil case with fastening elements in the pool, characterized in that the pencil case is detachable in a plane perpendicular to its generatrix, and with a seal at the junction. 2. The device according to claim 1, characterized in that the lower part of the pencil case is provided with a vertical guide formed by the continuation of part of its wall. The device according to claim 1, characterized in that the sealing cuff is mounted on a removable part of the pencil case.

Description

HPIEMHQE DEVICE FOR AGREES OF SHOTY NUCLEAR FUEL.

The utility model relates to the field of spent nuclear fuel (SNF) management, in particular, to the technology of transporting fuel assemblies from unloading and loading machines (REM) to a storage pool. The utility model can be used both at existing nuclear power plants and in the design of new power units.

The prototype of the proposed technical solution is a receiver for spent nuclear fuel, the details of which are contained in the work (K. Ostryanin et al. Storage of spent fuel at a gas station, collection of studies in the field of reprocessing irradiated fuel and waste disposal. Sterilization v Symptom of member countries CsV, Czechoslovakia, 1 Rianske Lazne, April 1981, cI-fI2). The receiving device is made in the form of a pencil case (case) with sealed walls, a bottom and fastening elements of its E pool. Loading and unloading of fuel assemblies is carried out through the open upper end of the device, which is placed on the water mirror of the SNF storage tank. The fuel assembly is loaded into the device by means of an REM, the design of which provides protection against SNF ionizing radiation. Subsequent removal of the fuel assembly from the receiving device is carried out by means of the lifting and handling equipment of the reactor hall, which does not contain any means of protection from SNF ionizing radiation.

lie the advantages of the prototype device are:

The need to raise the fuel assembly from the protective volume of the pool water when it is unloaded from the receiver, resulting in,

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a high level of radiation is created in the reactor room. The occurrence under these conditions of a possible failure in the operation of handling equipment is associated with high labor costs and dose costs for its elimination. In addition, a change in the environment: water-air-air-water leads to changes in the temperature of the fuel elements and reduces the corrosion resistance of the material of their shells.

The problem solved by the proposed technical solution is; the exception of the operation of extracting the fuel assembly from the protective environment of the pool when it is unloaded from the receiving device (pencil case, cover).

The technicality of the proposed technical solution lies in the fact that the receiver for spent nuclear fuel, containing a pencil case with its fastening elements in the pool, is made detachable in the plane perpendicular to its generatrix and with a seal at the junction. For ease of use, the lower part of the device is equipped with a vertical guide formed by the continuation of part of its wall, and the sealing cuff is mounted on the removable part of the pencil case. The length of the removable part of the pencil case is 1.2-g2 of the length of the fuel assembly from the condition that the required protective layer of pool water is available when removing fuel assemblies of various sizes and different sizes of residual energy from the receiver and transporting them to the pool.

The technical solution is illustrated by graphic material, where Fig. 1 shows a receiving device in section. In FIG. 2-g8 illustrates the sequence of transport operations with the fuel assembly unloaded from the reactor using a receiving device.

The receiving device (FIGL) consists of the lower part of the pencil case I and the removable part of the pencil case 2. The lower part of the pencil case I contains a vertical 1 - a nougat guide 3, a centering support flange 4, a support 5. lia an elastic element 6 is installed at the bottom of the bottom of the pencil case I. The removable part the case 2 contains a sealing sleeve 7 and a flange 8. The receiving device is located in the water pool 9. In the upper part of the pool 9, the receiving device is fixed with a folding claw 10, pivotally mounted on the bracket II. The bracket And is equipped with a limiter 12. lateral displacement of the suspension 13 of the fuel Assembly 14.

The operating procedure of the receiving device.

The receiving device (Fig. 1) is placed on the bottom of the pool 9 and is fixed by means of a gripper 10. 1 a PSlvi pin (not shown in the sketch) with the fuel assembly unloaded from the reactor, by means of the connecting pipe 15 (Fig. 2) with cuffs 16 are joined to the removable part of the canister 2 and unload the fuel assembly 14 into the cavity of the receiving device. In this case, the fuel assembly 14 is supported by the sealing plug 17 of the suspension 13 of the fuel assembly 14 on the upper end of the removable part of the canister 2. After the unloading of the fuel assembly 14 is completed (Fig. 3), the connecting pipe 15 is removed from the removable part of the canister 2 and the relay relay is withdrawn from of the receiving device 1./-;, to release the removable part of the pencil case 2 (Fig. 4) by means of the crane 18 and the gripper 19, the fuel assembly 14 with the suspension 13 is lifted and mounted on the stop 20 for dismantling the sealing plug 17. After dismantling the plug 17 (Fig. 5) fuel assembly 14 mouth poured onto the elastic element b. The released removable part of the canister 2 (Fig. 6) by means of the crane 18 and the gripper 21 is removed from the vertical guide 3 of the lower part of the canister I. Then, by means of the gripper 19 (Fig. 7), the fuel assembly 14 with the suspension 13 is suspended on the crane hook 18 and is removed from the bracket II socket. The assembly assembly 14 with the suspension 13 is lifted by the crane 18. After the lower end of the fuel assembly 14 exits from the cavity of the lower part of the canister I, its further lifting is stopped and moved under the protective layer of pool water to the place where the following technol Logical operations: separation of the suspension 13 from the fuel assembly 14, the next storage stage, etc.

Technology using the proposed receiving device may have other options. For example, in FIG. shows the operation of the proposed receiving device with the installation of the fuel assembly 14, unloaded from the machines P3: 1, by means of the sealing plug IV of the suspension 13 onto the upper end of the vertical guide 3 of the lower part of the canister I. The position numbers in FIG. corresponds to the item numbers shown in FIG. 1-g8. Figure 9 shows the unloading of the fuel assembly 14 by means of a connecting pipe 15 to the receiving device. FIG. 10 shows a receiver after removing the connecting pipe 15. FIG. II shows the operation of transporting the removable part of the pencil case 2. In FIG. 12-g13 shows the operations of transportation and placement of the fuel assembly 14 in the protective environment of the pool.

The implementation of the proposed technical solution allows to increase the safety of the technology when handling spent nuclear fuel and the safety of the operation of gas stations.

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Claims (3)

1. The receiving device for spent nuclear fuel containing a pencil case with fastening elements in the pool, characterized in that the pencil case is detachable in a plane perpendicular to its generatrix, and with a seal at the junction.  2. The device according to claim 1, characterized in that the lower part of the pencil case is provided with a vertical guide formed by the continuation of part of its wall.  3. The device according to p. 1, characterized in that the sealing cuff is mounted on a removable part of the pencil case.