Shell model in-water frequencies of the core barrel
Description
Natural frequencies of a 1/24th-scale core barrel/vessel model in air and in water are measured by determining frequency responses to applied forces. The measured data are analyzed by the use of the one-dimensional fluid-structure computer code, MULTIFLEX, developed to calculate the hydraulic force. The fluid-structure interaction in the downcomer annulus is computed with a one-dimensional network model formed to be equivalent to two-dimensional fluid-structure interaction. The structural model incorporated in MULTIFLEX is substantially simpler than that necessary for structural analyses. Proposed for computation of structural dynamics is the projector method than can deal with the beam mode by modal analysis and the other shell modes by a direct integration method. Computed in-air and in-water frequencies agree fairly well with the experimental data, verifying the above MULTIFLEX technique
Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Title
- Proceedings of the ANS/ASME/NRC international topical meeting on nuclear reactor thermal-hydraulics: PWR and BWR reactor-plant performance analysis and containment technology
- Journal Page Range
- p. 707-732.
- Report number
- NUREG/CP--0014(Vol.1)
Conference
- Title
- ANS/ASME topical meeting on reactor thermal-hydraulics.
- Dates
- 9 - 12 Oct 1980.
- Place
- Saratoga, NY, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12641486
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CALCULATIONS; HYDRAULICS; HYDRODYNAMICS; LOSS OF COOLANT; MATHEMATICAL MODELS; MECHANICAL VIBRATIONS; PRESSURE GRADIENTS; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR SAFETY; STRESSES
- Descriptors DEC
- ACCIDENTS; CONTAINERS; FLUID MECHANICS; MECHANICS; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS