JPH02216093A - Refuelling device - Google Patents

Abstract

PURPOSE:To shorten a refuelling process by providing a sodium through-viewer to an articulated manipulator of a refuelling device. CONSTITUTION:At a time of refuelling, a refuelling device 5a having an articulated manipulator is placed on a roof slab 1 of a nuclear reactor vessel 7, and an upper structure 4 of a reactor core is raised upto a required altitude above a core fuel assembly 8 and is supported there. Then, an identification mark on an upper surface of an object assembly 8 is identified by a supersonic transducer 35 of a sodium through-viewer and the assembly 8 is grasped by a gripper 13. After that, the gripper 13 is raised by the manipulator to withdraw the assembly 8 and by a reverse procedure, a new assembly can be loaded into the reactor core.

Description

DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to a multifunctional refueling device for use, for example, in a liquid metal cooled fast breeder reactor.

(Prior art) The conventional refueling method is a combination of two sets of rotating plugs (referred to as double rotating plugs) on a roof slab (also referred to as a plug) that closes the upper end opening of the reactor vessel and a refueling device. It is carried out by The positioning and transfer of each core fuel l\ is mainly performed by rotating the double rotating plug. The attachment and detachment of the core fuel is carried out by the type 2 rotating plug twisting method using the fuel exchange device, or by the combination of an eccentric rotating plug and the rotation of the fuel exchange device which has an arm with a fixed eccentric length. Replacement is performed using a single-turn plug refueling method. In this way, various methods have been used depending on the purpose of manufacturing the equipment or minimizing the size of the reactor vessel. An outline of the fuel exchange system of the French Super Phoenix reactor, which is a typical conventional example described above, will be explained with reference to FIG. In Fig. 9, a large rotating plug 2 and a small rotating plug 3 are mounted on a roof slab 1 for closing off the upper part of the reactor vessel, and a core upper mechanism 4 and a fuel exchange device are mounted on the small rotating plug 3. 5 is installed.

(Problems to be Solved by the Invention) In order for the conventional fuel exchange device 5 to reach the required core position, it is necessary to perform positioning by rotating the large-rotation plug 2 and the small-rotation plug 3, respectively. Since core fuel is handled, the rotational positioning of each plug 2, 3 requires very precise operation.

On the other hand, since the roof slab containing the rotating plugs 2 and 3 plays the role of a lid for the reactor vessel 7, a sealing structure is required to prevent leakage of cover scum, and a rotational drive structure is required.
Incorporating this seal structure requires a considerable amount of space and mechanism.

In either method, the structure is complicated by the rotating plug, which requires a rotating drive structure and a sealing structure.

Increasing the size is unavoidable, and there are also problems such as a method lacking in speed due to the positioning of each fuel by a combination of mechanisms such as rotation.

Note that reference numeral 6 in FIG. 9 indicates a reactor core in which a large number of core fuel assemblies 8 are loaded in a reactor vessel 7, and this reactor core 7 is supported by a core support structure 9. Further, a circulation pump 11 and an intermediate heat exchanger 12 are attached to the roof slab 1.

The present invention has been made in order to solve the above-mentioned problems, and firstly, the fuel can be quickly approached and transferred directly to the fuel exchange device through the shortest route. Provide replacement equipment. Second, by eliminating rotating plugs and gaining direct access to the core fuel,
To avoid the restriction on the diameter of the reactor structure in the conventional fuel exchange system and to rationalize the structure and obtain a compact nuclear reactor. Thirdly, we provide a fuel exchange device that can improve the economic efficiency of the plant by utilizing a device that can be accessed anywhere and having multiple functions such as double-duty as an inspection device during the in-service life of the reactor. It's about doing.

[Structure 1 of the Invention (Means for Solving the Problems) In order to perform fuel exchange and transfer most efficiently, it is possible to perform fuel exchange and transfer using a fuel exchange device using the white body instead of relying on the assistance of other mechanisms such as a rotary plug as in the past. From access and positioning to each core
It is necessary to have a Q function. Therefore, in the present invention, a sodium fluoroscopy device with an eye function is incorporated at the tip to provide access positioning function to each reactor core, and a manipulator-type refueling device with multi-joint functions is used to visually perform operations inside the reactor in sodium. It is structured in a way that resembles the movements of a human with .

That is, the present invention is a multi-jointed bendable structure that is mounted on a roof slab that closes the upper end opening of a reactor vessel and that extends from the roof slab so as to be able to handle core components or 1F4 structures inside the reactor vessel. A manipulator is incorporated therein, and a sodium fluoroscopy device is attached to the gripper of this manipulator.

(Function) When exchanging fuel, the refueling device is installed on the roof slab of the reactor vessel, and the upper core mechanism is raised and held above the core fuel assembly. Next, the target core fuel assembly is identified and confirmed by ultrasonic oscillations of the sodium fluoroscopy device, and the core fuel assembly is grasped with a gripper. Thereafter, the gripper is raised using a manipulator to handle the core fuel assembly.

Load a new fuel assembly into the core at the location where it was removed by reversing the above procedure.

During operation, the ultrasonic oscillator 1 to the transducer are held perpendicular to the object to be inspected, and the object to be inspected is observed.

(Embodiment) An embodiment of the fuel exchange device according to the present invention will be described with reference to FIGS. 1 to 8.

FIG. 1 is a diagram showing an example of a tank-type fast breeder reactor to which the present invention is applied, and the same parts as in FIG. 9 are given the same reference numerals, and the explanation of the overlapping parts is omitted.

The embodiment of FIG. 1 differs from FIG. 9 in that the roof slab 1 is integrated with a multifunctional fuel exchange device that can eliminate the large-rotation plug 2 and the small-rotation plug 3.
It is because it is installed on top.

Specifically, what is indicated by reference numeral 5a is an articulated manipulator type fuel exchange device having multiple functions according to the present invention.

By the way, the solid line a in the figure shows the situation during fuel exchange in the fuel exchange device 5a, and the broken line in the figure shows the situation when the inside of the reactor vessel 7 is inspected during its service life. .

FIG. 2 shows a detailed overall configuration of the fuel exchange device 5a according to the present invention in a front view. This fuel exchange device 5a has a plurality of IJIiillo (10A, 10B-10C
) and the cross-gear shown enlarged in FIG.

The joints of the respective shells 10 constitute pressure boundaries using expansion joints 14 (metal bellows, etc.) formed of thin metal plates so as to be bendable.

In addition, the upper part is provided with a flange 15 that is attached to the end of the body 10.
is fixed to the roof slab 1 and supports the fuel exchange device 5a. Next, the details of the multi-joint part (part A in Figure 2) are explained in the third section.
Not shown in the figure. The first torso 10A and the second torso 10B (are connected by the Talosshaft (~19), and the winter clothes 10A,
103 (the J section is rotatable as shown by the arrow). Also, the connection between the winter clothes 10A and IOB is connected with an expansion joint 14 made of a thin metal plate, and the joint inside the reactor vessel 7 The bending motion of the shell 10B (arrow C in the figure) is made to prevent the sodium from leaking. 17 and the first worm wheel 18 to change the direction of rotation at right angles, and transmit the rotational force of the worm wheel 18 as it is to the second worm wheel 111ii 1103.
B rotates in the direction of arrow C. Further, the first worm 17 is connected to a first bearing 20 installed on the cross shaft 19.
is rotatably supported. Next, rotation in the direction of arrow C is performed by the same driving method as described above. In this case, the second drum 21 is rotatably supported by a second bearing 23 installed in the first barrel 10A. These mechanisms allow the barrel 103 to rotate freely in the directions of arrows C and D relative to the barrel 10A. The second arm 21 is engaged with and rotates by the second arm foil 22. Note that 24 in the figure indicates the second flexible shirt 1.

Next, FIG. 5 shows the detailed structure of the gun 1 nopper 13 (an enlarged view of FIG. 2B), which has a core fuel gripping/release operation and an inspection function during service life.

The grip d3 of the core fuel assembly and the finger 25 that performs the release operation are rotatably attached to the third shell 10G by a plurality of pins 26. In the grasping/releasing operation (arrow E in FIG. 5), the tapered portion of the claw opening/closing rod 27 comes into contact with the inside of the fin car 25 due to the vertical movement (arrow "" in FIG. 5) of the claw opening/closing rod 27 provided between the fin cars 25. This opens and closes the finger 25. The vertical movement of the claw opening/closing rod 27 is converted into rotational movement by the combination of the rack 28 and pinion 29 provided at the top. The movement is performed by changing the direction of movement to a right angle by an A-m wheel 31 provided at the tip of the third flexible shaft 32 extending from the outside of the reactor vessel 7 (butt A-m 30 and pinion 29). The opening and closing operations are performed.The third l]1iillO
The outside of c is moved by a mechanism similar to the hold down tube 33 or the body of the claw opening/closing rod 27 so that the surrounding fuel is not lifted up when handling the core fuel.

The tip of the gripper 13 is formed into a tapered shape so that it can be easily inserted into the core fuel 8, and the tip of the gripper guide tube 34 has an identification value bar 2 of the core fuel assembly 8 to be handled and an inspection function during service life. Ultrasonic oscillation 1 ~ Lance Dury
35 is installed (pushed).This transducer 35
Observation is made using an MI cable 36 extending from the furnace outside the furnace (not shown). Since these mechanisms and parts penetrate the pressure boundary of the nuclear reactor, they are sealed with an expansion joint 37 made of a thin metal plate and a cable penetration (not shown). d5, the finger 25 opens and closes to the left and right using the pin 37 as a fulcrum. An expansion joint 38 is connected to the upper part of the claw opening/closing rod 27.

Next, the operation of the fuel exchange device having the above configuration will be explained. At the time of fuel exchange, the fuel exchange device 5a stored outside the reactor is inserted from the top into the opening for installing the fuel exchange device in the roof slab 1 attached to the top of the reactor vessel 7 (closed with a door valve, etc. during reactor operation). Load and set f=f.

Next, the upper core mechanism 4 installed on the core fuel assembly 8 is raised upward to a required position and held. As a result, there is no device on the core fuel assembly 8 that would interfere with the refueling operation. Next, when handling the target core fuel assembly 8, when handling it at the tip of the fuel exchange device 5a, the core fuel assembly is After confirming the identification mark on one side of the body 8, the core fuel assembly 8 is grasped by the gripper 13 at the tip of the fuel exchange device 5a.

Thereafter, the winter version 10 of the fuel exchange device 5a bends and moves the gripper 12 upward and forward (see FIGS. 6 and 7). Insert it into the desired position by reversing the procedure. With this method, it is possible to insert the fuel only by operating the fuel exchange device 5, and there is no need for assistance in moving the equipment, and the fuel exchange operation can be performed in the shortest possible time.

Next, if the inspection function is to be used during the identification management of core components and the service life of reactor internals, tc+ is shown in Figure 8.
The ultrasonic generator 30 installed at the tip of the gripper 13 is held at a right angle position to the object 39 to be inspected, and the object to be inspected is observed.

The advantages of this embodiment are that, since a rotating plug with a complicated structure is not required, it is possible to achieve a one-egg reactor structure with the minimum size of necessary functions, and that the operation mechanism is not concentrated in the fuel exchange device, and the operation mechanism is not concentrated in the fuel exchange device. It has the following advantages: it can be removed, making overall maintenance easier, the time required for fuel exchange and transfer can be shortened, and it can also be used as an in-core inspection device.

In addition to the above-mentioned embodiment, if the same fuel exchange device as in this embodiment is installed in the upper part of the core gM 16'+ 4, and it is used for both inoperable and rotational operations, further compactness and economical effects can be obtained. In addition, in this example, the power from the drive mechanism installed outside the furnace was used to drive the long flexible shirt 1~, but the same effect can be obtained by using electric motors that can withstand high temperatures in each joint part. You can get results.

[Effects of the Invention] According to the present invention, by eliminating the rotating plug, the roof slab structure is greatly simplified, and the structure of the nuclear reactor 4? 'l
By minimizing the building dimensions (in the radial direction), there is a significant reduction in the amount of materials that comes from converting to compact 1, and the T by minimizing the fuel exchange route.
The economic effect of shortening the culm is very large. In addition, since the entire fuel exchange system has been integrated into the fuel exchange equipment, port 2 can be removed during reactor operation, making maintenance etc. possible when the reactor is not in use, making it possible to improve operating efficiency and reliability. It will be a contribution.

Furthermore, since it can also be used as a device for inspecting the inside of the reactor and detecting damage, it is possible to reduce the amount of equipment required.

[Brief explanation of the drawing]

FIG. 1 is a schematic cross-sectional view showing a fast breeder reactor equipped with a fuel exchange device according to the present invention, FIG. 2 is an overall configuration diagram showing an embodiment of the fuel exchange device according to the present invention, and FIG. A vertical cross-sectional view showing an enlarged view of part A in Fig. 2, and Fig.
FIG. 5 is an enlarged longitudinal cross-sectional view of section B in FIG. 2, and FIGS. 6 and 7 show the state during fuel extraction according to the present invention. FIG. 8 is a conceptual diagram illustrating the situation when inspecting the inside of a reactor according to the present invention, and FIG. 9 is a cross-sectional view showing a conventional fuel exchange device and a fuel exchange system using a double rotating plug. 1... Roof slab 2... Large rotation plug 3... Small rotation plug 4... Core upper mechanism "+ 'i R01, dA *I Z"J&i
l! 6...Reactor core 7...Reactor vessel ε3...Core fuel assembly 9...Core support structure 1()...Channel 11...Circulation pump 2...Intermediate heat exchanger 3...・・Gripper 4・・Expansion joint 5・・Flange 6・・First flexible shaft 7・・71-m 8・・A-m wheel 9・・Tarosjiya 71~20・・・Bearing 21...A-m 22...A-m wheel 23...Bearing 24...Second flexible shaft 25...Fin blade 26...Pin 27... Claw opening/closing rod 28...Rack 29...Pinion 30...Tem 31...Tem wheel 32...Third flexible shifter 33...Hold down tube 34...Gripper Guide tube 35...Transducer core 36...Ml cable 37...Pin 38...Expansion joint 39...Object to be inspected (~ 1~ "1 -~-1n8

Claims (1)

[Claims] An articulated bendable manipulator is installed on a roof slab that closes the upper end of the reactor vessel and extends from the roof slab so as to be able to handle core components or reactor internals within the reactor vessel. , and a sodium fluoroscopy device is attached to the gripper of the manipulator.