Nuclear power station fuel cladding failure diagnosis system and diagnosis method thereof

Abstract

The invention provides a nuclear power station fuel cladding failure diagnosis system and diagnosis method thereof. The nuclear power station fuel cladding failure diagnosis system comprises a nuclideconcentration measuring module, a measuring data processing module and a failure diagnosis module, wherein the nuclide concentration measuring module is arranged outside a nuclear power station primary loop pipeline and used for measuring photon number and photon energy released by each radionuclide in a nuclear power station primary loop coolant within a preset time section; the measuring data processing module is used for receiving the photon number and the photon energy within the preset time section and extracting characteristic nuclide and concentration thereof from the photon number andthe photon energy within the preset time section according to characteristics of the photon energy released by the radionuclide and photon emissivity within a unit time; and the failure diagnosis module is used for receiving the characteristic nuclide and the concentration thereof, adopting a self-evolution diagnosis algorithm to process and analyze the characteristic nuclide and the concentration thereof and diagnosing whether the fuel cladding is broken or not. According to the nuclear power station fuel cladding failure diagnosis system and diagnosis method, online continuous monitoring and diagnosis of nuclear power station fuel cladding integrity during power operation period are realized, and self-evolution of the diagnosis algorithm is also realized.

Description

technical field [0001] The invention relates to the technical field of nuclear power, in particular to a nuclear power plant fuel cladding damage diagnosis system and a diagnosis method thereof. Background technique [0002] At present, domestic methods for monitoring fuel cladding damage in nuclear power plants mainly include: regular manual sampling analysis, total γ on-line monitoring and off-line sipping. Manual periodic sampling analysis method: refers to the periodical sampling of the primary loop coolant through the nuclear sampling system of the nuclear power plant during the operation of the nuclear power plant. The radioactivity concentration of the main characteristic nuclides in the agent. Compare the radioactivity concentration of the characteristic nuclides with the radiochemical technical specifications of the nuclear power plant, and then judge whether the fuel cladding of the nuclear power plant is damaged. The total gamma on-line monitoring method: refers...

AI Technical Summary

Problems solved by technology

[0003] At present, the deficiencies of fuel cladding damage monitoring technology in PWR nuclear power plants in service in China are mainly reflected in: manual periodic sampling and sample pretreatment take a long time, and the online continuous monitoring and diagnosis of fuel cladding integrity and cladding damage related parameters cannot be performed; γOn-line monitoring can reflect whether the fuel cladding is damaged in real time, but it cannot determine the number of damaged cladding, the size of the breach, and the burnup range of the damaged component; offline sipping can only complete the monitoring of the integrity of the fuel assembly after shutdown Execute the detection of fuel cladding integrity and its damaged cladding parameters during power operation, the off-line sipping process is complicated, and the detection takes a long time

[0004] Therefore, the diagnostic methods of the prior art cannot monitor the number of cladding damages, the size of the groove, and the fuel consumption range of the damaged components online in real time during power operation. Changeable, unable to self-evolve with measured data

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