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Data acquisition and processing system of reactor core neutron fluence rate

A technology of neutron fluence rate and data acquisition, which is applied in reactors, nuclear reactor monitoring, nuclear power generation, etc., to achieve high measurement accuracy, ensure system reliability, and strong processing and error correction capabilities

Active Publication Date: 2011-06-01
SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

All of these pose challenges to the method and device design of data acquisition and data processing in the core neutron fluence rate data measurement system

Method used

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  • Data acquisition and processing system of reactor core neutron fluence rate
  • Data acquisition and processing system of reactor core neutron fluence rate
  • Data acquisition and processing system of reactor core neutron fluence rate

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Embodiment Construction

[0016] The present invention will be described in detail below in conjunction with the accompanying drawings and embodiments.

[0017] This embodiment is a measurement example of the core neutron fluence rate of a 300MWe pressurized water reactor. In the 300MWe power nuclear reactor core, there are 121 fuel assemblies. According to the principle of uniform distribution in 3 fuel partitions and 4 quadrants, 30 fuel assemblies are selected to be installed with flux rate measuring tubes (also known as bushings). . 21 of them are fuel assemblies representing different situations, and 9 are fuel assemblies representing repeated symmetries. The distribution of measuring pipes in the core is shown in figure 2 .

[0018] like figure 1 As shown, the core neutron fluence rate data acquisition and processing system provided by the present invention includes a core nuclear testing device and a data processing device, wherein the core nuclear testing device includes a plurality of mea...

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Abstract

The invention belongs to the field of reactor core power monitoring of reactors in nuclear power plants, and in particular, relates to data acquisition and processing system of reactor core neutron fluence rate. The system comprises core testing device and data processing device. The core testing device comprises multiple measuring cabinets and one synchronously shared cabinet. Measuring cabinetsand the synchronously shared cabinet are respectively connected to the mobile detector in core through the measuring pipe. Each measuring cabinet has a corresponding mobile detector and multiple mobile detectors are installed in different measuring pipes which are different from their neutron fluence rate. There are two data processors in the data processing device. One connects to the measuring cabinet containing core testing device to realize the acquisition of data. Real-time communication between the first and second processor is ensured. The second processor will carry out the real-time response to the signals collected by the first processor including test of the abnormal temporal logic signals and error correction for analog signals of neutron fluence rate.

Description

technical field [0001] The invention belongs to the field of nuclear power plant reactor core power monitoring, in particular to a core neutron fluence rate data collection and processing system. Background technique [0002] The power measurement of nuclear power plant reactor is an important part of reactor control and safety protection. Taking the pressurized water reactor as an example, the core power distribution is generally monitored by detecting the neutron fluence rate distribution of the nuclear reactor core. The existing pressurized water reactor neutron measurement system is divided into reactor neutron measurement system and external neutron measurement system. [0003] The neutron measurement system in the reactor is used to measure the neutron fluence rate distribution of the core, so as to check the neutron measurement system outside the reactor, provide fuel burnup data, verify the reactor burnup design for reasonable refueling, and realize fuel optimizatio...

Claims

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Application Information

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IPC IPC(8): G21C17/10
CPCY02E30/30
Inventor 王志成谢大蓉毛磊马骏方舟
Owner SHANGHAI NUCLEAR ENG RES & DESIGN INST CO LTD
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