Analysis of impact phenomena between PWR fuel assemblies in earthquake situations
Description
To qualify fuel assembly seismic resistance and to promote the development of new grid designs, FRAMATOME (Fuel Division) in cooperation with CEA have launched a large scale experimental program which will lead to the design of improved models for safety analyses. The tests performed on full scale mock-ups were devoted to analyse: - the vibratory behaviour (frequency, damping) of the fuel assembly as a function of two important parameters: the motion amplitude and the holddown force. The effect of the fluid on these characteristics has been also investigated. - The behaviour of the assemblies during impacts (impact against a rigid wall and impact between two assemblies). The aim of this paper is to present the main results of these tests and the modelisation of the fuel assembly, developed to interpret these tests. Some correlations between experimental and calculation results will be shown
Availability note (English)
MF available from INIS under the Report Number.Files
20042355.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 24 p.
- Report number
- CEA-CONF--9699
Conference
- Title
- Vibration and Seismic response of Fluid-Structure Systems.
- Acronym
- ASME Pressure Vessel and Piping Conference
- Dates
- 19-23 Jun 1988.
- Place
- Pittsburgh, PA (USA).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 20042355
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DAMPING; EARTHQUAKES; EIGENFREQUENCY; FUEL ASSEMBLIES; IMPACT SHOCK; OSCILLATION MODES; PWR TYPE REACTORS; REACTOR CORES; SEISMIC EFFECTS; TEST FACILITIES
- Descriptors DEC
- ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS