DocumentCode
3019964
Title
System identification of nuclear reactor by dynamic data system methodology
Author
Chow, M.C. ; Wu, S.
Author_Institution
University of Wisconsin-Madison, Madison, Wisconsin
fYear
1977
fDate
7-9 Dec. 1977
Firstpage
868
Lastpage
874
Abstract
A new modeling technique called Dynamic Data System (DDS) is used to identify the nuclear reactor dynamics using operating neutron flux data. The identification of the reactor dynamic characteristics is carried out by properly choosing the sampling interval and sample length. The internal lumped temperature feed-back time constant ??t can be identified from the operating data for the High Flux Isotope Reactor (HFIR) and the Oconee Power Reactor. The ??t value for the HFIR is found increasing from .08 sec. to .35 sec. during a 23 day fuel cycle operation. The ??t value for the Oconee reactor is found to be approximately 3 seconds. In addition, two abnormal frequency peaks are identified during the control rod bearing failure in HFIR. One frequency is always exactly twice as large in value as the other, e.g., 5.4 Hz vs. 2.7 Hz. These two frequencies are found shifting during the cycle operation.
Keywords
Autoregressive processes; Data systems; Differential equations; Frequency; Inductors; Isotopes; Neutrons; Power generation; System identification; Temperature control;
fLanguage
English
Publisher
ieee
Conference_Titel
Decision and Control including the 16th Symposium on Adaptive Processes and A Special Symposium on Fuzzy Set Theory and Applications, 1977 IEEE Conference on
Conference_Location
New Orleans, LA, USA
Type
conf
DOI
10.1109/CDC.1977.271691
Filename
4045961
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