Published 1980
| Version v1
Report
Engineering research in nuclear components, pt. 1
- 1. Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.
Description
A flow-induced vibration analysis technique and a procedure to predict fretting wear damage from experimental data are presented. Examples are used to illustrate these techniques. (auth)
Additional details
Additional titles
- Subtitle (English)
- Vibration and fretting wear of heat exchangers
Publishing Information
- Imprint Title
- Heat exchanger reliability
- Imprint Pagination
- 180 p.
- Journal Page Range
- p. 29-36.
- Report number
- INIS-mf--6612
Conference
- Title
- Canadian Nuclear Association Heat Exchanger Reliability Seminar.
- Dates
- 1 May 1980.
- Place
- Toronto, Canada.
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 12627643
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; FLOW STRESS; HEAT EXCHANGERS; MATHEMATICAL MODELS; MECHANICAL VIBRATIONS; PERFORMANCE TESTING; PREDICTION EQUATIONS; STEAM GENERATORS; STRESS ANALYSIS; WEAR
- Descriptors DEC
- BOILERS; EQUATIONS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; STRESSES; TESTING; THERMAL REACTORS; VAPOR GENERATORS
Optional Information
- Notes
- 8 refs.