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Multi-input and multi-output path group selector for reactor core neutron flux measurement

A multi-input, multi-output, flux measurement technology, applied in reactors, nuclear reactor monitoring, nuclear power generation, etc., can solve problems such as long delivery cycle, probe stuck, untimely maintenance service, etc., and achieve compact structure and high reliability Effect

Active Publication Date: 2020-04-17
NO 719 RES INST CHINA SHIPBUILDING IND
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, since the neutron probe and the connected cables need to travel about 15 meters in the entire channel, and pass through multiple components and pipes, it is easy to cause the probe to be stuck in actual use
However, there is only one channel in the core of the existing road group selector. When the probe is stuck, the remaining nine measurement channels will also be unusable, which seriously affects the accuracy of drawing the core power distribution map.
In addition, imported equipment is expensive and has a long delivery cycle, and maintenance services are not timely

Method used

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  • Multi-input and multi-output path group selector for reactor core neutron flux measurement
  • Multi-input and multi-output path group selector for reactor core neutron flux measurement
  • Multi-input and multi-output path group selector for reactor core neutron flux measurement

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Embodiment Construction

[0020] The technical solutions in the present invention will be clearly and completely described below in conjunction with the accompanying drawings and embodiments.

[0021] Such as figure 1 , figure 2 , image 3 , Figure 4 As shown, this embodiment provides a multi-input and multi-outlet road group selector for core neutron flux measurement, including an inlet selection mechanism, a channel selection mechanism, and an outlet merging mechanism.

[0022] The entrance selection mechanism is composed of an entrance shell 3, a tapered guide hole 1, a paddle 2 and two guide tubes 4. One end of the tapered guide hole 1 is conical, and the other end is a waist-circle channel with the size of two probe sections. , the two passages are set up and down side by side, so that the probes entering from the outside can enter the waist-circle passage through the tapered guide surface; the pick 2 is placed in the upper and lower passages of the tapered guide hole 1, and the pick 2 is in ...

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Abstract

The invention belongs to the technical field of nuclear power station reactor core measurement, and provides a multi-input and multi-output path group selector, which is used for a nuclear power station reactor core neutron flux measuring system and comprises an inlet selecting mechanism, a channel selecting mechanism and an outlet merging mechanism, wherein the channel selecting mechanism internally comprises two mutually independent connecting pipes, and two neutron probes capable of entering from the inlet selecting mechanism can penetrate out from any two of ten channels of the outlet merging mechanism. According to the invention, the path group selector is compact in structure and high in reliability, wherein when a certain path is jammed, the rescue channel is opened, so that the measurement of the other nine channels can be continuously completed.

Description

technical field [0001] The invention belongs to the technical field of nuclear power plant core measurement, and specifically relates to a multi-input multi-output road group selector, which is used in a nuclear power plant core neutron flux measurement system. Background technique [0002] As a large, complex and highly safety-demanding system, a nuclear reactor must accurately determine its various operating state parameters, among which parameters such as the neutron flux distribution in the core are important parameters for the operator to control the reactor under normal conditions , also provides important data for the operator to take necessary mitigation measures in the event of an accident. The nuclear power plant core neutron flux measurement system can intermittently measure the neutron flux distribution map of the reactor according to the needs of the unit operation, draw the core power distribution map, and use it to calibrate the threshold value of the nuclear ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C17/108
CPCG21C17/108Y02E30/30
Inventor 蔺常勇沈明明孙祁祝娇张淮超徐卫锋王东芹郑文祥
Owner NO 719 RES INST CHINA SHIPBUILDING IND