Pressurized water reactor nuclear power station control bar driving mechanism on-line monitoring and fault diagnosing method

A technology of pressurized water reactor nuclear power plant and driving mechanism, which is applied in nuclear power generation, nuclear reactor monitoring, reactor, etc.

Active Publication Date: 2007-11-07
NUCLEAR POWER QINSHAN JOINT VENTURE
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

But it only issues control commands, measures the displacement to verify the function of the driving mechanism

Method used

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  • Pressurized water reactor nuclear power station control bar driving mechanism on-line monitoring and fault diagnosing method
  • Pressurized water reactor nuclear power station control bar driving mechanism on-line monitoring and fault diagnosing method
  • Pressurized water reactor nuclear power station control bar driving mechanism on-line monitoring and fault diagnosing method

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Experimental program
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Embodiment Construction

[0015] There are 33 bundles of control rods for Qinshan Phase II Reactor. 8 shutdown rod bundles and 25 regulation rod bundles are used to adjust the power of the reactor. Eight shutdown rod bundles are compiled into a rod group——Sa, and Sa is divided into two subgroups, Sa1 and Sa2, and each subgroup contains 4 rod bundles. The 25 adjustment rod bundles are compiled into four rod groups A, B, C and D, and the three rod groups A, B and C are divided into two subgroups 1 and 2 respectively; A1, A2, B1, B2, C1 and D each Contains 4 bundles, C2 only contains 1 bundle. Correspondingly, there are 33 control rod drive mechanisms, and each subgroup is controlled by a power cabinet, a total of 9 power cabinets.

[0016] Each driving mechanism has 3 coils, and 3 current signals need to be measured. If the sound and vibration signals for judging the movement of the mechanism are added, each driving mechanism has 4 signals to be collected. 132 signals need to be collected for 33 drivi...

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Abstract

This invention provides an on-line monitor and fault diagnosis method for PWR nuclear power plant including the following steps: 1, data collection, 2, digit filtration and pre-process, 3, acquiring extremum points to carry out polygon process to the waveforms, 4, merging the extremum points and eliminating single peaks, 5, identifying character points of the waveforms in terms of upgrading, transmission and keeping to check current and waving amplitude, 6, judging step sequence and operation time and diagnoses fault, 7, comparing the consistency of four rod-beam operations of a sub-set to estimate them according to deviations and finish single-step analysis of the sub-set waveform, 8, collecting and displaying waveforms, storing effective data and storing action recordings.

Description

technical field [0001] The invention relates to an on-line monitoring method, in particular to an on-line monitoring and fault diagnosis method of a control rod driving mechanism of a pressurized water reactor nuclear power plant. Background technique [0002] Control Rod Drive Mechanism (hereinafter referred to as CRDM: Control Rod Drive Mechanism) is the only movable part in the nuclear reactor pressure vessel. Its failure or performance degradation may cause sticking and sliding rod accidents, which seriously affect the availability of the unit. The rod control equipment of units 1 and 2 of Qinshan Phase II has set up a monitoring circuit for the coil current and ripple of the driving mechanism. The current fault diagnosis is realized by hardware, and it is not combined with the timing sequence of the driving mechanism action command. Only one alarm value for excessive current and one alarm value for low current can be set, and it cannot monitor whether the large current ...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C17/00
CPCY02E30/30
Inventor 昌正科董治国苑成光常乐莉唐意于龙吴金标
Owner NUCLEAR POWER QINSHAN JOINT VENTURE
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