Published 1985
| Version v1
Book
Response of an immersed elastic tube bundle to pressure transients
Description
The response of the control rod guide tubes of a pressurized water nuclear reactor to the pressure transient caused by a reactor vessel outlet pipe break loss-of-coolant accident is studied by the homogenization technique. The method is used to investigate acoustic phenomena due to the compressibility effects in the flow during such a transient. An equivalent medium is derived by likening the dynamic equations of the coupled fluid-tube system. Numerical procedures are presented briefly
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (USA)
- Imprint Title
- Fluid transients in fluid-structure interaction - 1985
- Journal Page Range
- p. 63-68.
Conference
- Title
- American Society of Mechanical Engineers winter annual meeting.
- Dates
- 17-21 Nov 1985.
- Place
- Miami, FL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18037663
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPRESSION; CONTROL ELEMENTS; ELASTICITY; HYDRAULICS; LOSS OF COOLANT; PIPES; PRESSURE DEPENDENCE; PRESSURE GRADIENTS; PWR TYPE REACTORS; REACTOR VESSELS; RESPONSE FUNCTIONS; SOUND WAVES; TRANSIENTS; TUBES
- Descriptors DEC
- ACCIDENTS; CONTAINERS; ENRICHED URANIUM REACTORS; FUNCTIONS; MECHANICAL PROPERTIES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS