Published 1985
| Version v1
Book
Cross-flow induced vibration of U-bend tubes of steam-generator tubes
Creators
- 1. CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Dept. d'Etudes Mecaniques et Thermiques
Description
This paper presents the results of a series of tests performed on two U-bend tube models subjected to water cross-flow. These models are representative of a PWR steam generator. The first one simulates the innermost part of the bundle, the second one the external part of it. The main results discussed in this paper are the spectral characteristics of turbulent excitation in single phase cross flow, fluidelastic instability and non linear interaction between tubes and tube supports. (orig.)
Additional details
Publishing Information
- Publisher
- North-Holland.
- Imprint Place
- Amsterdam (Netherlands)
- ISBN
- 0444 86960 3
- Imprint Title
- Transactions of the 8. international conference on structural mechanics in reactor technology. Vol. F1 and F2
- Imprint Pagination
- 547 p.
- Journal Page Range
- p. 229-234.
Conference
- Title
- 8. international conference on structural mechanics in reactor technology (SMIRT-8).
- Dates
- 19-23 Aug 1985.
- Place
- Brussels (Belgium).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 17017388
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DAMPING; FLOW RATE; FLUID-STRUCTURE INTERACTIONS; FREQUENCY DEPENDENCE; INSTABILITY; MECHANICAL VIBRATIONS; PWR TYPE REACTORS; RESPONSE FUNCTIONS; STEAM GENERATORS; TUBES; TURBULENT FLOW; VELOCITY
- Descriptors DEC
- BOILERS; ENRICHED URANIUM REACTORS; FLUID FLOW; FUNCTIONS; POWER REACTORS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- EUR--10001 DE/EN/FR.