KONCEPCE DIAGNOSTICKÉHO SYSTÉMU RVMS A EXPERIMENTÁLNÍ PODPORA JEHO NASTAVENÍ

Abstract cze:
Abstrakt: This contribution deals with the functional description and initial setting of the Reactor Vibration Monitoring System (RVMS) that is supplied as a part of the Temelin Monitoring and Diagnostic System (TMDS). The purpose of the RVMS module for NPP Temelin is to measure the vibration characteristics of reactor pressure vessel, vessel core barrel and associated internal structures as well as fuel assemblies. The vibration characteristics of the steam generator at Unit 1 and coolant pressure fluctuations at Unit 2 are also monitored. This is accomplished by monitoring the following parameters: ex-core neutron noise, in-core neutron noise, temperature, mechanical acceleration and pressure fluctuation signals. For setting of the initial parameters into the RVMS and for identification of individual spectra amplitude peaks, it was necessary to carry out the large-scaled experiment, which was designed for identification of the lowest natural frequencies and vibration mode shape estimations of the VVER 1000 reactor pressure vessel and internals and one of the cooling loops. Evaluation of the experiments was made both in time and in frequency domain. The identified values will be further used for updating of the existing mathematical models using the parametric identification method.

Abstract eng:
Abstract: This contribution deals with the functional description and initial setting of the Reactor Vibration Monitoring System (RVMS) that is supplied as a part of the Temelin Monitoring and Diagnostic System (TMDS). The purpose of the RVMS module for NPP Temelin is to measure the vibration characteristics of reactor pressure vessel, vessel core barrel and associated internal structures as well as fuel assemblies. The vibration characteristics of the steam generator at Unit 1 and coolant pressure fluctuations at Unit 2 are also monitored. This is accomplished by monitoring the following parameters: ex-core neutron noise, in-core neutron noise, temperature, mechanical acceleration and pressure fluctuation signals. For setting of the initial parameters into the RVMS and for identification of individual spectra amplitude peaks, it was necessary to carry out the large-scaled experiment, which was designed for identification of the lowest natural frequencies and vibration mode shape estimations of the VVER 1000 reactor pressure vessel and internals and one of the cooling loops. Evaluation of the experiments was made both in time and in frequency domain. The identified values will be further used for updating of the existing mathematical models using the parametric identification method.

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