Mass, stiffness, and damping identification for a pressurized water reactors fuel assembly by a proper orthogonal decomposition method
Creators
- 1. CEA Cadarache DEN/DTN/STRI/LHC, Saint Paul-Lez-Durance Cedex 13108, (France)
Description
In this paper, dynamic tests of a fuel assembly subjected to an axial flow are presented. Tests are performed for various flow conditions, at several displacement amplitudes. The first four modes of the fuel assembly are excited, two confinements are tested. A parameters identification method based on a proper orthogonal decomposition (POD) analysis is proposed. Mass, damping, and stiffness parameters are presented for different displacement amplitudes and flow rates. An added mass effect in still water is observed, and the damping increases linearly with the flow rate. A nonlinear behavior of the fuel assembly is observed. An added stiffness effect increasing with the flow rate is observed, and the mass seems to depend on the flow rate. The by-pass seems to be responsible for these observations. (authors)
Availability note (English)
Available from doi: http://dx.doi.org/10.1115/1.4028559Additional details
Identifiers
- DOI
- 10.1115/1.4028559;
Publishing Information
- Journal Title
- Journal of Pressure Vessel Technology
- Journal Volume
- 136
- Journal Page Range
- p. 061303.1-061303.9
- ISSN
- 0094-9930
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 47102687
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S58: GEOSCIENCES;
- Descriptors DEI
- BYPASSES; DAMPING; EARTHQUAKES; FLEXIBILITY; FLOW RATE; FUEL ASSEMBLIES; MASS; PWR TYPE REACTORS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; SEISMIC EVENTS; TENSILE PROPERTIES; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 17 refs.