Computer Modeling of Flow Induced In-Reactor Vibrations

by Peter Turula, (A.M.ASCE), Mechanical Engineer; Components Tech. Div., Argonne National Lab., Argonne, Ill.,
Thomas M. Mulcahy, Mechanical Engineer; Components Tech. Div., Argonne National Lab., Argonne, Ill.,


Serial Information: Journal of the Power Division, 1977, Vol. 103, Issue 1, Pg. 37-50


Document Type: Journal Paper

Abstract: An assessment of the reliability of finite element method computer models, as applied to the computation of flow induced vibration response of components used in nuclear reactors, is presented. The prototype under consideration was the East Flux Test Facility reactor being constructed for US-ERDA. Data were available from an extensive test program which used a scale model simulating the hydraulic and structural characteristics of the prototype components, subjected to scaled prototypic flow conditions as well as to laboratory shaker excitations. Corresponding analytical solutions of the component vibration problems were obtained using the NASTRAN computer code. Modal analyses and response analyses were performed. The effect of the surrounding fluid was accounted for. Several possible forcing function definitions were considered. Results indicate that modal computations agree well with experimental data. Response amplitude comparisons are good only under conditions favorable to a clear definition of the structural and hydraulic properties affecting the component motion.

Subject Headings: Computer models | Vibration | Finite element method | Scale models | Data processing | Model tests | Hydraulic models

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