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System for monitoring pressure vessel of reactor of nuclear power station and method thereof

A technology for nuclear power plant reactors and pressure vessels, which is applied in the field of nuclear power, can solve the problems of high cost of thermocouples, difficult to judge the validity of structural damage measurement signals, and difficult to determine the installation location. Response time requirement reduction effect

Active Publication Date: 2014-12-10
中广核工程有限公司 +1
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0004] The technical problem to be solved by the present invention is to judge whether the reactor has melted through the thermocouple at the bottom of the reactor cavity in the prior art, the cost of the thermocouple is high, the installation position is difficult to determine, there is a danger of structural damage, and the validity of the measurement signal is difficult. To provide a monitoring system and method for reactor pressure vessels of nuclear power plants with low requirements for thermocouples, easy determination of installation positions, and high validity of measurement signals

Method used

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  • System for monitoring pressure vessel of reactor of nuclear power station and method thereof
  • System for monitoring pressure vessel of reactor of nuclear power station and method thereof
  • System for monitoring pressure vessel of reactor of nuclear power station and method thereof

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Embodiment Construction

[0043] In order to make the object, technical solution and advantages of the present invention clearer, the present invention will be further described in detail below in conjunction with the accompanying drawings and embodiments. It should be understood that the specific embodiments described here are only used to explain the present invention, not to limit the present invention.

[0044] The invention provides a monitoring system for a reactor pressure vessel of a nuclear power plant. The temperature information of the reactor pressure vessel can be collected from time to time by a monitoring terminal arranged at a monitoring point of the reactor pressure vessel, and the state of the reactor pressure vessel can be monitored through a monitoring device.

[0045] image 3 It is a structural schematic diagram of a monitoring system 100 for a reactor pressure vessel of a nuclear power plant according to the present invention. Such as figure 2 and 3 As shown, the monitoring s...

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Abstract

The invention relates to the technical field of nuclear power and discloses a system for monitoring a pressure vessel of a reactor of a nuclear power station and a method thereof. The monitoring system contains a monitoring terminal which is disposed at the monitoring point of the monitored pressure vessel of the reactor and is used to acquire and send temperature information of the pressure vessel of the reactor; and a monitoring device which is electrically connected with the monitoring terminal and is used to receive the temperature information sent from the monitoring terminal and monitor the state of the pressure vessel of the reactor according to the temperature information. According to the invention, as there is no need to contact high temperature melts, the cost of the monitoring terminal can be reduced, its installation position is easy to determine and the acquired temperature information is effective and reliable. Based on the temperature information, the state of the pressure vessel of the reactor can be effectively monitored. The system for monitoring the pressure vessel of the reactor of the nuclear power station has a simple structure and requires low cost. The monitoring method provided by the invention is convenient to carry out and has high accuracy.

Description

technical field [0001] The invention relates to the technical field of nuclear power, and more specifically, to a monitoring system and method for a reactor pressure vessel of a nuclear power plant. Background technique [0002] Reactor Pressure Vessel (RPV) is a cylindrical vessel in a pressurized water nuclear reactor, which includes the core of the nuclear reactor and is vertically arranged in the reactor cavity. Under normal circumstances, the pressurized water cools the core, so the temperature of the core and the reactor pressure vessel fluctuates in a small range. However, after a severe accident (such as an unexpected stop of core cooling), the reactor core may melt and further cause the reactor pressure vessel to melt through, with serious consequences. [0003] In the Fukushima nuclear power plant accident in Japan, due to the lack of corresponding means to monitor the reactor pressure vessel, the effectiveness of external water injection after the accident could ...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C17/00
CPCY02E30/30
Inventor 唐华雄张宏亮田亚杰李公杰董孝胜
Owner 中广核工程有限公司
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