Pressurized water reactor driving line cold test device

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

Active Publication Date: 2014-04-09
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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  • Pressurized water reactor driving line cold test device
  • Pressurized water reactor driving line cold test device

Examples

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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 pressurized water reactor driving line cold test device. The pressurized water reactor driving line cold test device comprises a top cover simulation assembly and a hanging basket simulation assembly which are located between a control rod driving mechanism and a guide cylinder assembly. The top cover simulation assembly and the hanging basket simulation assembly are connected to form a cavity structure, and a control rod guide assembly is further installed in the cavity. The upper end of the control rod guide assembly is connected with the control rod driving mechanism, the lower end of the control rod guide assembly is connected with a hoarding assembly, simulation fuel and a control rod assembly are located in the hoarding assembly, and a pressing simulation assembly is further installed between the control rod guide assembly and the hanging basket simulation assembly. The pressurized water reactor driving line cold test device has the function of performing tests on the rod falling characteristic of the control rod assembly by simulating a prototype reactor and performing test research on the influences on the rod falling performance in different operation environments with driving line eccentricity and flow changes, the obtained test results are accurate and can be used for testing design reasonability and reliability of a control rod driving line guide structure, and a necessary test basis is provided for the design of a driving 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 Applications(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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