JPH07146394A - Method for identifying control number of nuclear fuel assemblies - Google Patents

Abstract

PURPOSE:To enable the mistake-free, easy and quick identification to be effected adopting a method for identifying control numbers written on upper nozzles and the like in order to control nuclear materials of fuel assemblies. CONSTITUTION:In a nuclear fuel assembly A, bar codes 10a, 10b and 10c are printed on the lateral and upper sides of upper nozzles 1 and the sides of lower nozzles 2. During the process for the transportation of the nuclear fuel assembly A in a core pool 11 and a fuel storage pool 14, for example, a reader 19a, which is installed in the side of the lower end of freely descendable cylinders 12b and 17b in fuel handling cranes 12 and 17, reads the bar code 10b and introduces the read signal of it into a computer 20. Moreover, readers 19b and 19c are installed respectively in a fuel conveying passage 16 and a fuel inspection device 18 so as to read the bar codes 10a and 10c, which enables the computer control as a system.

Description

Detailed Description of the Invention

[0001]

The present invention relates to a nuclear fuel assembly,
During its storage and combustion in the reactor, control of nuclear fuel materials (counting control) and physical protection (Physical P
For the sake of protection), a management number identification method of a nuclear fuel assembly suitable for identifying the nuclear fuel assembly by reading the management number displayed in the proper place of the nuclear fuel assembly without error. It is a thing.

[0002]

2. Description of the Related Art As is known, for example, in a fuel assembly for a pressurized water reactor, an upper nozzle 1 and a lower nozzle 2 are connected by a required number of control rod guide tubes 3 as shown in FIG. In addition, a large number of fuel rods 4 erected from the lower nozzle 2 are supported in a aligned state by a plurality of support grids 5. In FIG. 3, 1a is a hold-down spring and 1b is a clamp part. , This clamp part 1
A large-diameter pin hole 1c and a small-diameter pin hole 1d for the fuel handling crane are appropriately opened upward in b, 1e is a clamp screw, 1f is a water flow hole, 1g is a fixing hole for the control rod guide tube 3. Shows.

In order to manage the nuclear fuel assembly as described above as described above, a control number of about 4 to 6 digits of alphanumeric characters has been used so far on the side surface of the upper nozzle 1 and the upper surface of the clamp portion. Is engraved so that it can be visually identified. However, once the nuclear fuel assembly is burned, it is in a high radioactivity state, which makes it inaccessible to humans, which makes identification difficult. Therefore, the management number will be identified using a TV camera, etc., but this is also determined by a person looking at the screen,
It is easy to make an incorrect identification.

[0004]

SUMMARY OF THE INVENTION The present invention has been studied in view of the above-mentioned problems of the prior art, and it is not based on the above-mentioned upper nozzles or lower nozzles of the nuclear fuel assembly but inscribed in place, but by electrolytic polishing. In addition to the bar code of the bar code, a bar code reader is installed separately in the core pool, the fuel storage pool, and the fuel transfer passage that connects the two pools. By introducing the read signal of
The control number of the nuclear fuel assembly can be identified easily and quickly without relying on humans, and the bar code can be displayed in a small area so that it can be eaten anywhere. It is easy to manage the position of the body and the calculation of the amount of uranium as a system.
That is the purpose.

[0005]

In order to achieve the above-mentioned object, the present invention provides one of the side surface of the upper nozzle of the nuclear fuel assembly, the upper surface of the clamp portion and the side surface of the lower nozzle.
At one or more arbitrarily selected locations, a bar code as a control number is laid out by electrolytic polishing or the like, and this bar code is used for the core pool, the fuel handling crane in the fuel storage pool, and the core pool. One or more of arbitrarily selected ones of the fuel transfer passage for transferring the nuclear fuel assemblies whose direction is changed by the respective fuel turntables installed in the fuel storage pool and the fuel inspection device installed in the fuel storage pool. A control number identifying method of a nuclear fuel assembly, wherein a reader is installed at a location so that the reader can read the bar code and the read signal is input to a computer. Trying to provide.

[0006]

According to the present invention, in the upper nozzle of the nuclear fuel assembly, if the bar code as the control number is laid out on the upper surface of the clamp portion, the fuel can be used in the core pool or the fuel storage pool. When the nuclear fuel assembly is suspended by a handling crane, for example, in the case of a fuel handling crane in which a tubular body is fitted to the nuclear fuel assembly in order to prevent rolling during transfer. Since a bar code reader is attached to the lower part of the cylindrical body, the bar code of the clamp part can be read during a transfer operation for a series of nuclear fuel assemblies. Therefore, it is possible to identify the management number quickly and accurately without misunderstanding.

If the above-mentioned bar code is laid out on the side surface of the upper nozzle or the side surface of the lower nozzle, the nuclear fuel assembly is located in the core pool, and the direction is changed by the fuel turntable installed on the core pool. Then, in order to transfer this to the fuel turntable in the adjacent fuel storage pool, the bar code is read by the reader installed in the fuel transfer passage provided between both pools, also during a series of work steps. You will be able to Further, by providing a reader in the fuel inspection device provided in the fuel storage pool, it is possible to identify the bar code in the upper nozzle and the lower nozzle.

[0008]

EXAMPLE A method according to the present invention will be described below with reference to FIGS.
This will be described in detail with reference to the above, the side surface of the upper nozzle 1 has a bar code 10a, the upper surface of the clamp portion 1b has a bar code 10b, and the side surface of the lower nozzle 2 has one or more bar codes 10c. Select the word to eat. As a method of attaching the barcodes 10a, 10b, 10c, for example, by pressing a metal material or the like heated to a high temperature onto the upper nozzle 1 or the like, the surface is blackened by oxidation, or a barcode-like shape is formed on the desired surface. After the groove is formed, it is subjected to an oxidation blackening treatment in high temperature air or high temperature steam, and then by polishing the surface, only the groove becomes black. Here, needless to say, not only the bar code but also the above-mentioned indicia that can be identified by humans may be added together as in the conventional case.

If the black portion which is the bar code is made to be a groove as described above, after the irradiation of the nuclear fuel assembly, the clad which is the scale-like substance in the reactor water is irradiated on the black portion. However, the black bar code becomes clear by lightly brushing the surface of the upper nozzle or the like when the bar code adheres more than other parts, which makes it easier to identify and the bar code is not clear. This is because the upper nozzle 1 and the lower nozzle 2 are made of stainless steel, and the above-mentioned clad adhesion state is generally loose.

As described above, in the nuclear fuel assembly, not only the bar codes 10a, 10b and 10c are laid out at desired positions, but also bar code readers are selected at the following positions. , This is also one or more. That is, in the core storage pool 11 as shown in FIG. 1, the nuclear fuel assembly A is transferred in a suspended state by the fuel handling crane 12 as is known, but the existing manipulator crane is used. Then, at this time, the connection tool 1
The upper nozzle 1 can be suspended by the 2a, and the tubular body 12b is fitted on the nuclear fuel assembly A after the suspension is completed.

When this state is reached, the nuclear fuel assembly A concerned is installed in the core pool 11 of the fuel turntable 1
After being placed in the third storage body 13b, the storage body 13b is laid down about the rotation center 13a as shown by the arrow, and then the fuel turntable 1 in the adjacent fuel storage pool 14 is placed.
5 is transferred by a fuel transfer passage 16 such as a belt conveyor.

Next, the transferred nuclear fuel assembly A is contained 13b in the fuel turntable 15 on the fuel storage pool 14 side.
At the same time, it stands up as shown by the arrow, and this is suspended by the fuel handling crane 17 of the fuel storage pool 14 and stored in the fuel inspection device 18 provided therein. Here, in the drawing, 17a is a connecting member, and 17b is the tubular body of the fuel handling crane 17, which is the same as the tubular body 12b.

Therefore, according to the present invention, the reader 1 is located at a desired position in the transfer process of the nuclear fuel assembly A as described above.
One or more of 9a, 19b, 19c and 19d are installed as follows. Here, the reader 19a is attached to the inside of the lower end side of the tubular body 12b of the above-mentioned fuel handling crane 12, so that the tubular body 12b is the upper surface of the nuclear fuel assembly A. When facing each other, the reader 18a can read the bar code 10b erected on the upper surface of the clamp part 1b in the upper nozzle 1, and the read signal can be read by the computer 20.
To introduce.

If necessary, a reader 18b is also provided in the fuel transfer passage 16 so that the bar code 10c attached to the side surface of the lower nozzle c of the nuclear fuel assembly A during transfer is provided. , The above reader 19b
And read the read signal into the computer 20.

Further, a reader 19c is also installed in the lower end side of the cylindrical body 17a of the fuel handling crane 17 in the fuel storage pool 14 so that the bar code 10b of the upper nozzle 1 can be read and read. The signal can also be introduced into the computer 20. In FIG. 1, not only this but also the fuel inspection device 18 of the fuel storage pool 14 is provided with the reader 19d,
The selected bar code of the nuclear fuel assembly A is made readable, which is also connected to the computer 20.

[0016]

Since the present invention is carried out as described above, the nuclear fuel assembly can be identified by reading the bar code, so that the identification can be made without misidentification without danger to the human body. Can be done quickly. Moreover, since the reader is installed in the middle of the process of the transportation inspection of the nuclear fuel assembly, and this read signal is introduced into the computer, the position of the nuclear fuel assembly,
It becomes easier to manage the calculation of uranium amount as one system, and of course, the barcode can be eaten in a small area, so it can be displayed in a desired narrow space compared to the engraved space in the conventional method. .

[Brief description of drawings]

FIG. 1 is a vertical cross-sectional front view showing the vicinity of a core and a fuel storage pool showing an embodiment of a management number identifying method of a nuclear fuel assembly according to the present invention.

FIG. 2 is a partially cutaway front view showing bar code eclipse positions of a fuel assembly for a pressurized water reactor.

FIG. 3 is a perspective view of an upper nozzle in FIG.

[Explanation of symbols]

 1 Upper Nozzle 1b Clamping Part 2 Lower Nozzle 10a Bar Code 10b Bar Code 10c Bar Code 11 Core Pool 12 Fuel Handling Crane 12b Cylindrical Body 13 Fuel Turntable 13b Storage 14 Fuel Storage Pool 15 Fuel Turntable 16 Fuel Transfer Passage 17 Fuel Handling crane 17b Cylindrical body 18 Fuel inspection device 19a Reader 19b Reader 19c Reader 19d Reader 20 Computer A Nuclear fuel assembly

Claims (1)

[Claims] 1. A bar code as a control number by electrolytic polishing or the like at one or more positions arbitrarily selected from the side surface of the upper nozzle of the nuclear fuel assembly or the upper surface of the clamp portion and the side surface of the lower nozzle. This bar code is transferred to the nuclear fuel assemblies whose direction has been changed by the fuel handling cranes in the core pool and fuel storage pool, and the respective fuel turntables installed in the core pool and fuel storage pool. The bar code is read by the reader by installing the reader at one or more arbitrarily selected locations of the fuel transport passage and the fuel inspection device installed in the fuel storage pool. Then, the read signal is inputted to the computer, and the control number identifying method of the nuclear fuel assembly is characterized.