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A nuclear power plant reactor control rod addressing device and method

A nuclear power plant reactor and control rod technology, applied in the field of nuclear power plants, can solve the problems of increasing the burden on operating personnel, increasing the uncertainty of experiments, and increasing the risk of communication failure, so as to improve work efficiency and safety, reduce the risk of human failure, and reduce Communication Failure Risk Effects

Active Publication Date: 2020-10-13
CHINA GENERAL NUCLEAR POWER OPERATION +2
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0012] 1. The main control operator is required to perform a large number of operations, which increases the burden on the operating personnel, increases the risk of human failure, and is not conducive to the state control of the unit;
[0013] 2. The control rod has moved, which changes the reactivity of the primary circuit, which is not conducive to the reactivity control;
[0014] 3. It is necessary to communicate with the operator multiple times, which increases the risk of communication failure;
[0015] 4. The operator needs to perform a large number of unit state control tasks such as temperature increase and pressure increase, resulting in multiple interruptions of the addressing test, and an addressing test lasts from 5 to 20 hours, increasing the uncertainty of the test

Method used

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  • A nuclear power plant reactor control rod addressing device and method
  • A nuclear power plant reactor control rod addressing device and method
  • A nuclear power plant reactor control rod addressing device and method

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Embodiment

[0055] The nuclear power plant reactor control rod addressing device of this embodiment includes a plurality of control rods, a driving power supply, a lifting coil LC, and a voltage detector. Each control rod is provided with a lifting coil LC, but it is necessary to ensure that the control rods and the lifting coils are preset. Correspondence.

[0056] refer to figure 1, is a schematic structural diagram of the rod position probe 10 . The rod position probe 10 includes a fixed flange 101, a connector 102, a primary coil 103, a shield 104, a coil holder 105, a secondary coil 106, an auxiliary coil 107, an adjustment spring 108, and an intermediate washer 109; preferably, the secondary coil 106 The number of auxiliary coils 107 is five, and the number of auxiliary coils 107 is two. Wherein the primary coil 103, the secondary coil 106, and the auxiliary coil 107 are all wound on the coil holder 105, the primary coil 103 is connected to the AC power supply through the connecto...

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PUM

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Abstract

The invention relates to a nuclear power plant reactor control rod addressing device and method. The device includes a plurality of control rods, a driving power supply, a lifting coil LC, and a voltage detector; the control rod includes a rod position probe and a rod travel cover, and the rod position probe and the lifting coil LC are installed on the rod travel cover, and the rod position probe and the rod travel cover The lifting coil LC is coaxially installed; the rod probe includes secondary coils; the driving power is connected to each lifting coil LC, and the voltage detector is respectively connected to the secondary coil of each rod probe; one of the driving power is connected to the lifting coil LC, The lifting coil LC generates a first induced magnetic field, and the secondary coil coaxially arranged with the lifting coil LC generates a first induced voltage under the action of the first induced magnetic field, and the voltage detector completes the addressing of the control rods by detecting the first induced voltage. By implementing the invention, the workload of the operator can be reduced, the risk of human failure, the risk of communication failure can be reduced, and the work efficiency and safety can be greatly improved.

Description

technical field [0001] The invention relates to the field of nuclear power plants, and more specifically relates to a device and method for addressing control rods of nuclear power plant reactors. Background technique [0002] The control rod control system is one of the special systems for nuclear power plants. It includes two parts: the rod control system and the rod position measurement system. Its cables span the reactor bridge to connect the equipment on both sides. The joints of the rod control cable and the rod test cable are all disconnected, and the cables need to be reconnected after the refueling is completed and the big cover is closed to ensure the availability of the RGL system. [0003] For example, in M310 and CRP1000 reactor types, there are 61 rod control cables and rod test cables respectively. Address test to confirm that there is no crossover in its connection. The current addressing test method is as follows: [0004] 1. Block all rod bundles in a ro...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C17/10
CPCG21C17/10G21C17/00
Inventor 张军高夫领刘美军李生茂孙波罗红波王斌蔡达水犹代伦
Owner CHINA GENERAL NUCLEAR POWER OPERATION