This paper designs a measure and analysis system of nuclear noise frequency spectrum for narrow channel research reactor core. Based on high-speed synchronization DAQ which is PXI-1031, the hardware design has been carried out. By using Labview, the data acquisition and analysis code has been developed. In order to verify the function of nuclear noise frequency spectrum measure and analysis system, firstly, through using arbitrary waveform generator which is Fluke-282, two sine signals have been tested. Secondly, by using history operation datum, the prompt neutron decay constant has been measured and analyzed. The simulation experimental and operational datum results show that such measure and analysis system of nuclear noise frequency spectrum is successful and reliable design, which can meet the design requirements. Finally, the preliminary research work between helium bubble and its responding frequency for narrow channel core has just started to monitor safety operation or carry out fault diagnosis.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5145-6
PROCEEDINGS PAPER
The Design of Nuclear Noise Frequency Spectrum Analysis System and Helium Bubble Movement Behavior Computation for Narrow Channel Core
Herong Zeng,
Herong Zeng
China Academy of Engineering Physics, Mianyang, China
Search for other works by this author on:
Baoxin Yuan
Baoxin Yuan
China Academy of Engineering Physics, Mianyang, China
Search for other works by this author on:
Herong Zeng
China Academy of Engineering Physics, Mianyang, China
Baoxin Yuan
China Academy of Engineering Physics, Mianyang, China
Paper No:
ICONE26-81170, V003T02A007; 8 pages
Published Online:
October 24, 2018
Citation
Zeng, H, & Yuan, B. "The Design of Nuclear Noise Frequency Spectrum Analysis System and Helium Bubble Movement Behavior Computation for Narrow Channel Core." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory. London, England. July 22–26, 2018. V003T02A007. ASME. https://doi.org/10.1115/ICONE26-81170
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