A Drilling Device for Release of Fission Gas from Heavy Water Reactor Fuel Elements

A fuel element and fission gas technology, which is applied in boring/drilling, drilling/drilling equipment, and components of boring machines/drilling machines, etc., can solve the problem that technical parameters are difficult to control, equipment maintenance is difficult, and mechanical piercing is difficult to popularize and use. And other issues

Active Publication Date: 2017-11-10
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

The release and collection devices of PWR fuel elements at home and abroad generally adopt the mechanical puncture method, mainly because the cavity volume of PWR fuel elements is large, the puncture position is basically unlimited, and parameters such as puncture depth and pressure are easy to control ; Due to the small volume of the free cavity of the heavy water reactor fuel element (about 0.5ml), which is similar to a solid core rod, and the impact of the fuel element support block on the sealing, the position of the puncture hole and the static sealing of the fuel element are difficult, and it is difficult to promote the use of mechanical puncture holes
Laser perforation, due to the strong laser energy, the device is installed in a hot chamber, and the technical parameters are not easy to control. The perforated cladding may damage the fuel pellets or even dissolve the fuel element. Long-term use makes equipment maintenance difficult.

Method used

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  • A Drilling Device for Release of Fission Gas from Heavy Water Reactor Fuel Elements
  • A Drilling Device for Release of Fission Gas from Heavy Water Reactor Fuel Elements
  • A Drilling Device for Release of Fission Gas from Heavy Water Reactor Fuel Elements

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Embodiment

[0032] Such as figure 1 , figure 2 A drilling device for the release of fission gas from heavy water reactor fuel elements is shown, including a frame, on which a sealing seat A4 is arranged, and a hole A for installing a heavy water reactor fuel element 3 is arranged in the sealing seat A4, and the sealing The seat A4 is also provided with a seal for sealing the gap between the heavy water reactor fuel element 3 and the hole A of the seal seat A4, the seal seat A4 is connected with a gas collection seat 5, and the gas collection seat 5 has a structure that runs through the gas collection seat 5 and is perpendicular to the gas collection seat 5. The through hole B of the hole A, and the hole C at one end of the communicating hole A and the through hole B are arranged on the sealing seat A4. The gas collection seat 5 is connected to the sealing seat B7 through the axially telescopic pipe fitting 6, and one end of the pipe fitting 6 communicates with the through hole At the ot...

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PUM

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Abstract

The invention discloses a drilling device for releasing the fission gas of heavy water reactor fuel elements, which comprises a frame, on which a sealing seat A (4) is arranged, and a sealing seat A (4) is arranged inside the sealing seat A (4) for installing heavy water reactor fuel elements ( 3) Hole A, seal seat A (4) is connected with gas collection seat (5), pipe fittings (6), seal seat B (7) and electric drill (8) in sequence, and the motor shaft connecting shaft (2) of electric drill (8) ), the shaft (2) is rotatably installed in the shaft hole of the seal seat B (7), the drill bit (1) is fixedly installed on the lower end of the shaft (2), and the drive of the electric drill (8) is fixedly installed on the frame device (9). The beneficial effect of the invention is that the fuel element of the heavy water reactor can be drilled in a highly radioactive environment, and the fission gas can be completely released.

Description

technical field [0001] The invention relates to the technical field of nuclear fuel cycle, in particular to a drilling device for releasing fission gas from heavy water reactor fuel elements. Background technique [0002] The measurement of fission gas release rate of reactor fuel elements is an important content of post-irradiation inspection, which provides a basis for evaluating the design, manufacture and performance improvement of heavy water reactor fuel assemblies and similar fuel assemblies. The piercing technology is to pierce the cladding of the fuel rod and release the fission gas completely by using the pressure difference. It is a key link in the analysis and measurement of the fission gas. There are two commonly used piercing methods: mechanical piercing and laser piercing. The release and collection devices of PWR fuel elements at home and abroad generally adopt the mechanical puncture method, mainly because the cavity volume of PWR fuel elements is large, the...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): B23B41/00B23B47/00
CPCB23B41/00B23B47/00
Inventor 邝刘伟江林志任亮余飞杨郭成明黄伟杰刘振川许德强
Owner NUCLEAR POWER INSTITUTE OF CHINA
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