PWR drive line cold state test device

A technology of cold test and driving line, which is applied in the field of reactor experimental verification devices, can solve the problems of no cold test of control rod driving line, no written records and products of control rod driving line cold test device, etc., to achieve The effect of precise test results

Active Publication Date: 2016-01-20
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0005] At present, there is no special device for the cold test of the control rod drive line, and there are no written records and products about the cold test device of the control rod drive line.

Method used

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  • PWR drive line cold state test device
  • PWR drive line cold state test device

Examples

Experimental program
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Embodiment

[0027] Such as Figures 1 to 2As shown, the PWR driving line cold test device of the present invention includes a simulated top cover assembly 2 and a simulated hanging basket assembly 4 positioned between the control rod drive mechanism 1 and the draft tube assembly 9, and the simulated top cover assembly 2 consists of a flower-shaped plate 201, positioning plate 202, and simulated top cover cylinder 203. The positioning plate 202 is fixed on the simulated top cover cylinder 203 through fasteners. The control rod driving mechanism 1 is fixed on the flower-shaped plate 201 by interference fit. Positioning holes with different misalignment median values ​​on the positioning plate 202, and then rotate the flower-shaped plate 201, so that the positioning pin holes on the flower-shaped plate 201 correspond to the pin holes with different misalignment median values ​​on the positioning plate 202, and then the prototype drive line can be simulated Different misalignment median value...

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Abstract

The invention discloses a cold-state test device for a drive line of a pressurized water reactor, which includes a simulated top cover assembly and a simulated hanging basket assembly located between the control rod drive mechanism and the guide tube assembly, and the simulated top cover assembly and the simulated hanging basket assembly are connected to form a cavity The body structure is also equipped with a control rod guide assembly in the cavity. The upper end of the control rod guide assembly is connected with the control rod driving mechanism, and the lower end of the control rod guide assembly is connected with the shroud assembly. The simulated fuel and control rod assemblies are located in the shroud assembly. A simulated pressing component is also installed between the control rod guide component and the simulated hanging basket component. The invention has the function of simulating the prototype stack to carry out the test of the drop characteristics of the control rod assembly and the influence of different operating environment conditions such as drive line eccentricity and flow change on the drop performance. The obtained test results are accurate and can be used to verify the control rods. The rationality and reliability of the design of the drive line guide structure provide the necessary test basis for the design of the drive line.

Description

technical field [0001] The invention relates to a device for reactor experiment verification, in particular to a cold-state test device for a drive line of a pressurized water reactor. Background technique [0002] The reactor control rod drive line is the only equipment unit with relative movement in the reactor body structure, and is the execution unit of the reactor control and nuclear safety protection system. It is composed of rod drive mechanism socket, control rod assembly, guide assembly and fuel assembly. [0003] The control rod drive line is very important in the operation of the reactor. The control rod assembly moves up and down in the guide assembly and the fuel assembly under the drag of the drive mechanism, so as to realize the start-up, power regulation, reactivity compensation, normal shutdown and Safe shutdown under accident conditions. [0004] In order to understand the impact of different operating environmental conditions (misalignment, flow changes,...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G09B23/20
Inventor 方才顺张宏亮罗英杜华陈训刚刘晓范恒周禹王留兵李燕王尚武
Owner NUCLEAR POWER INSTITUTE OF CHINA
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