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Detection apparatus for neutron flux and temperature of reactor core

A technology of detection device and neutron detector, which is applied in the direction of reactor, nuclear reactor monitoring, reduction of greenhouse gases, etc., can solve problems such as increasing the risk of leakage of reactor coolant

Active Publication Date: 2014-06-18
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

With this measurement method and measuring instruments, it is necessary to open holes at the bottom of the pressure vessel and install a large number of through pipes, which will increase the risk of reactor coolant leakage

Method used

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  • Detection apparatus for neutron flux and temperature of reactor core
  • Detection apparatus for neutron flux and temperature of reactor core
  • Detection apparatus for neutron flux and temperature of reactor core

Examples

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Embodiment Construction

[0026] The following combination figure 1 , figure 2 The present invention will be further described with examples.

[0027] There is a core neutron and temperature detection device used to measure the core neutron flux and the fuel assembly outlet temperature in the nuclear power plant reactor.

[0028] like figure 1 The present invention is a detecting device for neutron flux and temperature in the reactor core, including a component shell 5, a self-powered neutron detector group 6, a thermocouple 4, an internal sealing structure 3, a cold junction compensation device 2, Connector 1, end sealing plug 7;

[0029] The component housing 5 includes a first sleeve 501 and a second sleeve 502; the first sleeve 501 is an axially equal-diameter sleeve structure; the second sleeve 502 includes a large-diameter sleeve structure, a A small-diameter casing structure and a tapered tube structure connecting the large-diameter casing structure and the small-diameter casing structure; ...

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PUM

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Abstract

The invention relates to a detection apparatus for a neutron flux and a temperature of a reactor core. The detection apparatus comprises an assembly housing, a self-powered neutron detector set, an internal sealing structure, a connector and a terminal portion sealing plug, wherein the self-powered neutron detector set is fixed inside the assembly housing and comprises N self-powered neutron detectors, the N self-powered neutron detectors are uniformly arranged at intervals from bottom to top along the axial direction of the assembly housing, the connector is sealedly fixed on the upper end of the assembly housing, the terminal portion sealing plug is sealedly fixed on the lower end of the assembly housing, the internal sealing structure is sealedly fixed in the internal of the assembly housing positioned above the self-powered neutron detector set, and the armoured cables of the N rhodium self-powered neutron detectors are bundled up and fixed, upwardly extend along the axial direction of the assembly housing, penetrate through the internal sealing structure, and finally are fixed on the pin of the connector. According to the present invention, the neutron flux change of the reactor core can be rapidly responded, the reactor core neutron flux and the fuel assembly outlet temperature can be real-timely measured, and the design requirements of the transmission cable can be reduced.

Description

technical field [0001] The invention relates to the field of nuclear power plant reactor core neutron flux and temperature measurement, in particular to a detection device for reactor core neutron flux and temperature. Background technique [0002] Usually, in the reactor core of a nuclear power plant, core neutron and temperature measuring instruments are installed to measure the neutron flux of the core and the outlet temperature of the fuel assembly. The measured signals are used to monitor the three-dimensional power distribution of the core, the cooling state of the core, etc. Reactor operation. [0003] Different types of measuring instruments are installed in nuclear power plants of different reactor types. The existing measurement method is to use the measurement method of inserting a thermocouple from the top and inserting a miniature movable fission chamber from the bottom to measure the outlet temperature of the fuel assembly and the neutron flux of the core. Th...

Claims

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Application Information

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IPC IPC(8): G21C17/108G21C17/112
CPCY02E30/30
Inventor 杨戴博吕渝川何鹏袁彬何正熙李文平王华金苟拓刘艳阳李高
Owner NUCLEAR POWER INSTITUTE OF CHINA
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