A receiving unit for spent fuel assembly

 

(57) Abstract:

Usage: the device is intended for transportation teplosistema assemblies. The essence of the invention: a receiving unit for spent fuel assemblies containing foam with elements of its mounting in the pool, made a split in the plane perpendicular to its surface and seal in the joint. The lower part of the device is provided with a vertical guideway formed by the continuation of its walls, and the sealing sleeve mounted on the removable part of the case. The length of the removable part of the case is 1.2oC2,0 the length of the fuel Assembly. 1 C.p. f-crystals, 8 ill.

The invention relates to the field of spent nuclear fuel (SNF), in particular, to the technology of transportation of fuel assemblies from the unloading-loading machines (RCM), in the pool for storage. The invention can be used in existing nuclear power plants, and the design of new units.

The closest analogue of the proposed technical solution is a receptor for the spent fuel Assembly details of which are contained in the work. The receiver is designed in teplovidelyaushaya Assembly is made through the open upper end of the device, which is located above the water pool storage of spent nuclear fuel. Loading of the fuel assemblies in the device is performed by REM, in the construction which provides protection against ionizing radiation of spent fuel Assembly. Subsequent extraction of the fuel Assembly receiving device is performed by the handling equipment of the reactor hall, which does not contain protection against ionizing radiation of spent fuel Assembly.

The disadvantages of the device closest analogue is:

the necessity of lifting the fuel Assembly protective volume of pool water when it is unloaded from the receiving device in which the premises of the reactor hall creates a high level of radiation. The occurrence in these terms of possible failure handling equipment is associated with high labor costs and doses to eliminate it. In addition, changes in the environment: water air water leads to changes in the temperature of the fuel Assembly and reduces the corrosion resistance of the material of the shells.

The task of the proposed technical solution, so the bit device (pencil case, of the case).

The essence of the proposed technical solution is that the receiving device for spent fuel assemblies containing foam with elements of its mounting in the pool, made a split in the plane perpendicular to its surface and seal in the joint. For easy operation the lower part of the device is provided with a vertical guideway formed by the continuation of its walls, and the sealing sleeve mounted on the removable part of the case. The length of the removable part of the case is 1.2oC2,0 length fuel Assembly conditions the availability of the necessary protective layer of pool water when removing from the output device and the transportation pool teplovidelyaushaya assemblies of different sizes and different values of the decay power.

The technical solution is illustrated graphic material. In Fig.1 shows a receiving device in the incision. In Fig.2 a longitudinal section a-a receptor. In Fig.3 view B of Fig.1. Fig.4, 5, 6, 7, 8 the sequence of execution of transport operations with the fuel Assembly using the receiver.

The receiving device (pencil box) 1 (Fig.1) consists of a bottom part 2 and the EC 5, the support 6. At the bottom of the lower part 2 of the case 1 has an elastic element 7. The upper part 3 of the case 1 contains the gasket 8 and the flange 9. The case 1 is installed in a water pool 10. In the upper part of the basin 10 case 1 is fixed folding grip 11, hinged to the bracket 12. The bracket 12 is provided with a limiter 13 lateral displacement of the suspension 14 fuel Assembly 15 (Fig.4).

The receiving device (pencil box) 1 works as follows (Fig.4, 5, 6, 7). The case 1 is mounted on the bottom 16 of the basin 10 and fixed by capturing 11 (Fig.4). Unloading-loading machine (REM) (Fig. not shown) discharged from a reactor fuel Assembly 15, join with the upper part 3 of the case 1 through a connecting pipe 17 with cuffs 18 and do unloading of the fuel assemblies 15 in the case 1. In this case, a fuel Assembly 15 is backed by a sealing tube 19 of the suspension 14 fuel Assembly 15 on the upper end of the removable upper part 3 of the case 1. After unloading the fuel assemblies 15 are produced undocking REM with case 1 and the machine REM divert from the receiving device 1. To release the removable upper part 3 of the case 1 (Fig.5), through valve 20 and the grip 21 of the fuel is x2">

After dismantling of the tube 19 of the fuel Assembly 15 mounted on the elastic element 7 (Fig. 6). Liberated shoot the upper part 3 of the case 1 (Fig. 6) through the valve 20 and the grip 23, is removed from a vertical guideline 4 of the lower part 2 of the case 1, and the folding grip 11 folded. Further, through the seizure 21 (Fig.7) fuel Assembly 15 with the suspension 14 is suspended on the hook of the crane 20 and removed from the slot of the bracket 12, the limiter 13 lateral displacement of the suspension 14 fuel Assembly 15, and then, the fuel Assembly 15 with the suspension 14 is lifted by the crane 20. After the release of the lower end of the fuel Assembly 15 (Fig.7) from the cavity of the lower part 2 of the case 1, further lifting her stop and move under the protective layer of water in the pool 10 (Fig. not shown) to place the following technological operations: the Department of the suspension 14 from the fuel Assembly 15, etc.

Technology using the proposed receiving device 1 may have other options. For example, in Fig.8 illustrates the operation of the proposed receiving device 1 with the installation unloaded from the machine REM fuel Assembly 15 through the sealing tube 19 of the suspension 14 to the upper end of the vertical guide 4 n the Yemen device 1, undocking REM with the receiving device 1, etc. described previously and corresponds to the numbers of the positions indicated in Fig.4, 5, 6, 7.

Implementation of the proposed solution allows to increase the security technology of spent nuclear fuel and the safety of nuclear power plants.

1. A receiving unit for spent fuel assemblies containing foam, open top, with the fastening elements into the pool, wherein the housing case is made detachable in the plane perpendicular to its generatrix, and sealed at the interface of the two parts, and the length of the upper removable part of the case is 1.2 2.0 length of the fuel Assembly.

2. The device under item 1, characterized in that the lower part of a case provided with a vertical guideway formed by the continuation of its walls.

 

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