The present disclosure relates to the technical field of nuclear reactor fuel element preparation, and particularly to a spherical fuel element forming apparatus.
At present, the spherical fuel element used in pebble-bed High Temperature Gas-Cooled Reactor (HTR) has a diameter of 60mm, and includes fuel area and fuel-free area. The spherical fuel element as a whole is a graphite matrix, and the outer layer thereof is a fuel-free area with a thickness of about 5 mm. The basic structure of the spherical fuel element is that the fuel-free graphite spherical shell is filled with a dispersion fuel consisting of coated fuel particles and the graphite matrix.
The preparation process of the spherical fuel element includes: preparing matrix graphite powder, overcoating coated particles, pressing core sphere, pressing green sphere, turning, carbonization and high temperature purification, wherein the forming of green sphere fuel area and fuel-free area is the core technology in the spherical element manufacturing process. The process of forming the spherical fuel element includes mixing overcoated particles with the matrix graphite powder, charging the mixture into a rubber die and pressing into a core sphere, molding the fuel-free area in a final-pressing die, and finally obtaining the green which is slightly bigger than a target size by final-pressing. However, the prior art does not disclose specifically how to form the spherical fuel element, including how to mix the overcoating particles with the matrix graphite powder, how to press into the core sphere and how to form the spherical fuel element finally. Chinese patent application CN201210177503 discloses a quasi-isostatic pressing vacuum hydraulic machine, which is used for pressing the green of the spherical fuel element, but does not disclose other steps of forming the spherical fuel element, including the mixing of the overcoated particles and matrix graphite powder, and the technologies and apparatus used in the process of molding the fuel-free area in the final-pressing die etc. Therefore, it is of great importance to provide a spherical fuel element forming apparatus which is able to reduce the fuel element cost, has a compact structure and is convenient to operate.
The technical problem to be solved by the present disclosure is to provide a spherical fuel element forming apparatus which has a compact structure and is convenient to operate.
For this purpose, the present disclosure provides a spherical fuel element forming apparatus, comprising: a fuel area forming system, a fuel-free area shaping system and a green sphere pressing system connected sequentially.
The fuel area forming system is used for evenly mixing a core sphere matrix powder with nuclear fuel particles and then pressing the mixed core sphere matrix powder and nuclear fuel particles into core spheres.
The fuel-free area shaping system is used for preparing a spherical fuel element from the core spheres covered by a fuel-free matrix powder.
The green sphere pressing system is used for pressing the spherical fuel elements into green spheres.
Preferably, the fuel area forming system comprises a core sphere matrix powder quantitative conveying device, a nuclear fuel particle evenly-distributing device, a nuclear fuel particle accurate quantification device, a primary stirring device, a discharge molding device, a secondary stirring device and a core sphere pressing device arranged sequentially. The core sphere matrix powder quantitative conveying device, the nuclear fuel particle accurate quantification device, the primary stirring device and the discharge molding device are connected by a material canister workstation conveying device.
The core sphere matrix powder quantitative conveying device quantitatively conveys the core sphere matrix powder to the material canister workstation conveying device. The nuclear fuel particle evenly-distributing device and nuclear fuel particle accurate quantification device precisely and quantitatively conveys the nuclear fuel to the material canister workstation conveying device. The material canister workstation conveying device conveys the core sphere matrix powder and nuclear fuel to the primary stirring device. The primary stirring device stirs the core sphere matrix powder and nuclear fuel evenly. The material canister workstation conveying device conveys the core sphere matrix powder and nuclear fuel that passed through the primary stirring device to the discharge molding device. The discharge molding device fills a core sphere die with the core sphere matrix powder and nuclear fuel that are stirred evenly. The secondary stirring device stirs the core sphere matrix powder and nuclear fuel in the core sphere die.
The core sphere pressing device presses the core sphere matrix powder and nuclear fuel in the core sphere die into core spheres.
Preferably, the core sphere matrix powder quantitative conveying device comprises a first hopper for storing the core sphere matrix powder, and a spiral feeder at a bottom of the hopper, wherein a conveying amount of the core sphere matrix powder is controlled by a feeding time of the spiral feeder.
Preferably, the nuclear fuel particle evenly-distributing device comprises a rotatable second hopper for receiving nuclear fuel, a distribution tube connected with the second hopper and a plurality of columnar containers for receiving the nuclear fuel distributed by the distribution tube.
The nuclear fuel particle accurate quantification device comprises a balance with a bottom-suspension function, a weighing hopper suspended at a bottom of the balance and a vibrating feeder for adding nuclear fuel into the weighing hopper and capable of storing nuclear fuel.
The bottoms of the columnar containers are provided with tubes, through which the nuclear fuel in the columnar containers which are rotated in place is conveyed to the weighing hopper by rotations of the plurality of columnar containers.
Preferably, the material canister workstation conveying device comprises an infrared position sensor, a chain driven by a motor and a plurality of material canisters mounted on the chain. The infrared position sensor is used for determining whether the opens of the plurality of material canisters correspond to a conveying port of the core sphere matrix powder quantitative conveying device, a discharge port of a weighing hopper of the nuclear fuel particle accurate quantification device, the primary stirring device and the discharge molding device respectively.
Preferably, the secondary stirring device comprises a base plate for placing the core sphere die which is filled with the core sphere matrix powder and nuclear fuel, a bracket and a rotatable stirring head mounted on the bracket. The stirring head extends into an inner cavity of the core sphere die.
Under working conditions, the stirring head is driven by a motor to stir the core sphere matrix powder and nuclear fuel in the core sphere die. The base plate is driven by the motor to rotate, and a rotation direction of the base plate is opposite to that of the stirring head.
Preferably, the core sphere pressing device comprises an outer sleeve which can move up and down, an upper punch fixed in the outer sleeve and an lower punch which can move up and down. An outer diameter of the core sphere die is the same as an inner diameter of the outer sleeve, an outer diameter of the upper punch and an outer diameter of the lower punch respectively.
Preferably, the fuel-free area shaping system comprises a core sphere positioning-conveying device, a core sphere positioning-transferring device, a fuel-free area matrix powder quantitative conveying device and a fuel-free area shaping device arranged sequentially. The core sphere positioning-conveying device is connected with the fuel-free area shaping device through the core sphere positioning-transferring device. The fuel-free area matrix powder quantitative conveying device is connected with the fuel-free area shaping device.
The core sphere positioning-conveying device and core sphere positioning-transferring device transfer the core spheres to the fuel-free area shaping device. The fuel-free area matrix powder quantitative conveying device conveys the matrix powder to the fuel-free area shaping device. The fuel-free area shaping device coats the core spheres with the matrix powder so as to prepare the spherical fuel element.
Preferably, the core sphere positioning-conveying device comprises a disc which can be rotated positionally, wherein a plurality of bosses for placing the core spheres are distributed evenly on the disc.
The core sphere positioning-transferring device comprises a mechanical gripper and a mechanical arm for moving the mechanical gripper in a horizontal or vertical direction, wherein a moving range in the horizontal direction of the mechanical gripper is from right above the bosses of the core sphere positioning-conveying device to right above a die of the fuel-free area shaping device.
Preferably, the fuel-free area shaping device comprises a movable base plate for placing a die, a probe for detecting a level of matrix powder and an arc-shaped scraper for shaping the spherical fuel element. The center of the arc-shaped scraper is on a vertical axis of the die.
The spherical fuel element forming apparatus provided by the present disclosure is distributed according to a technical process flow line operation, is compact in structure and convenient to operate. All of the connections of the devices are reasonable. The apparatus operation has a good logical relationship and easily realizes automation. With the fuel-free area shaping system, the sphere greens after being finally pressed are high in sphericity. Only few finish allowance is needed, and the waste of graphite matrix powder is reduced and the fuel element cost lowered. In addition, with the nuclear fuel evenly-distributing device and nuclear fuel particle accurate quantification device, the obtained ratio of nuclear fuel and matrix powder is precise, therefore the finished product rate of the spherical fuel elements prepared by the spherical fuel element forming apparatus of the present disclosure is high.
The embodiments of the present disclosure will be described in detail with reference to the accompanying drawings hereinafter.
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Wherein preferably, the core sphere matrix powder quantitative conveying device 1 comprises a first hopper for storing the core sphere matrix powder and a spiral feeder at the bottom of the hopper, the conveying amount of the core sphere matrix powder is controlled by the feeding time of the spiral feeder. As shown in
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Wherein preferably, the fuel-free area shaping device comprises a movable base plate 11-1 for placing a die, a probe for detecting the level of matrix powder and an arc-shaped scraper 11-3 for shaping the spherical fuel element; the center of the arc-shaped scraper 11-3 is on the vertical axis of the die. Preferably, the lower hemisphere fuel-free area shaping device 11 comprises a rotatable base plate 11-1 for placing the lower half die of a final-pressing die, a bracket 11-2 which is driven by a cylinder and can move up and down, and an arc-shaped scraper 11-3 fixed vertically below the bracket, the base plate 11-1 is driven by a motor to rotate. A pair of probes for detecting the level of matrix powder is provided below the movable bracket 11-2, when the matrix powder reaches the probes, the lower hemisphere fuel-free area matrix powder quantitative conveying device 10 stops operation, meanwhile the cylinder pushes the movable bracket to move upward. Preferably, the upper hemisphere fuel-free area matrix powder quantitative conveying device 13 may comprise a base plate 13-1 for placing the upper half die of a final-pressing die, a pair of probes 13-2 for detecting the level of matrix powder, the base plate 13-1 is driven by a motor to rotate, the probes are on a powder-charge port of the final-pressing die, when the matrix powder reaches the probes, the upper hemisphere fuel-free area matrix powder quantitative conveying device 13 stops operation. Preferably, the upper, lower hemisphere fuel-free area shaping device may be 4 base plates uniformly distributed on a turnplate, wherein the 4 base plates may be respectively used for the fuel-free area shaping of the lower half die, placing the core sphere and covering with the upper half die, the fuel-free area shaping of the upper half die, and replacing the dies.
The green spheres which have a diameter slightly larger than a target size are pressed under a pressure no smaller than 300 Mpa by the final-pressing die after shaping of the fuel-free shaping system, and finally by the green sphere pressing system, wherein the green sphere pressing system may be a quasi-isostatic pressing vacuum hydraulic machine.
The processes of shaping the spherical fuel element and pressing the green spheres with the spherical fuel element forming apparatus above are as follows:
S1: a batch of graphite as the core sphere matrix powder and the fuel-free area matrix powder is charged into the first hopper of the core sphere matrix powder quantitative conveying device and the fuel-free area matrix powder quantitative conveying device respectively;
S2: when a material canister on the material canister workstation conveying device is right below the spiral feeder, a certain amount of graphite matrix powder is added into the material canister automatically;
S3: 98% of the weight of the nuclear fuel particles containing 250 gU are poured into the second hopper of the nuclear fuel particle evenly-distributing device, divided into 50 equal parts and stored in the columnar containers; the remaining 2% of the nuclear fuel particles are added into the vibrating feeder, the nuclear fuel particles in the columnar containers flow into the weighing hopper suspended at the bottom of the balance by the rotating of the columnar containers, the amount for fine adjustment is added by the vibrating feeder;
S4: when a material canister on the chain of the material canister workstation conveying device runs to be tight below the weighing hopper, the nuclear fuel particles in the weighing hopper are added in the material canister which has already contained quantitative graphite matrix powder;
S5: the chain of the material canister workstation conveying device conveys the material canister containing the nuclear fuel particles and graphite matrix powder to the workstation of the primary stirring device which stirs he nuclear fuel particles and graphite matrix powder evenly;
S6: the chain of the material canister workstation conveying device also conveys the stirred nuclear fuel particles and graphite matrix powder to the discharge molding device which fills the core sphere die with the stirred nuclear fuel particles and graphite matrix powder;
S7: the core sphere die filled with material is placed on the secondary stirring device to be stirred;
S8: the core sphere die filled with material is placed on the core sphere pressing device to be pressed into core sphere, and the pressed core spheres are placed on the bosses of the core sphere positioning-conveying device;
S9: the fuel-free area shaping device is started and the trunplate thereof rotates to 90 degrees, and drives the base plates on the turnplate, such that the lower half die in the base plate moves to the next workstation, the quantitative graphite matrix powder is conveyed to the lower half die by the lower hemisphere fuel-free area matrix powder quantitative conveying device;
S10: the core sphere positioning-conveying device is started and the mechanical arm controls the mechanical gripper to put the pre-pressed core spheres into the lower half die containing the graphite matrix powder, the core sphere is in the middle of a die cavity;
S11: the lower half die is covered with the upper half die, the trunplate of the fuel-free area shaping device is started to rotate another 90 degrees, such that the die moves to the next workstation, the upper hemisphere fuel-free area matrix powder quantitative conveying device injects quantitative graphite matrix powder into the die cavity of the die.
S12: then the dies are withdrawn from the turnplate of the fuel-free area shaping device and put into the quasi-isostatic pressing vacuum hydraulic machine to be pressed into green spheres.
The spherical fuel element forming apparatus provided by the present disclosure is distributed according to a technical process flow line operation, is compact in structure and convenient to operate. All the devices are connected rationally. The apparatus operation has a good logical relationship and easily realizes automation. With the fuel-free area shaping system, the sphere greens after being finally pressed are high in sphericity. Only few finish allowance is needed, and the waste of graphite matrix powder is reduced and the fuel element cost lowered. In addition, with the nuclear fuel particle evenly-distributing device and nuclear fuel particle accurate quantification device, the obtained ratio of nuclear fuel and matrix powder is precise, therefore the finished product rate of the spherical fuel elements prepared by the spherical fuel element forming apparatus of the present disclosure is high.
Although the embodiments of the present invention have been described in conjunction with the accompanying drawings, various modifications and variations can be made by those skilled in the art without departing from the spirit and scope of the present disclosure, and such modifications and variations are within the scope defined by the appended claims.
Filing Document | Filing Date | Country | Kind |
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PCT/CN2016/071573 | 1/21/2016 | WO | 00 |