Characterization of wear scars on fretted U-bend steam generator tubes
Description
The fretting scar geometry at the contact between the steam generator (SG) U-bend tube and the offset scallop bar support is analyzed to establish the relationship between the scar geometric characteristics and the operating conditions; namely, the tube orbital motion, alignment, axial motion, scar depth and scar volume. The fretting wear scars of two U-bend SG tubes removed from an operating CANDU nuclear steam generator were examined to determine various operating conditions at the tube/tube support interface. This information, which cannot be measured in-situ, is needed to justify assumptions used in numerical modelling of the tube/support dynamic interaction. To relate field measurements to laboratory-generated data base and code predictions, the relationship between the maximum wear depth and volumetric wear losses is investigated. The wide scatter in the variation of the average wear depth with the scar volume is significantly reduced by using a proposed weighted-average. 7 refs., 8 figs., 1 tab
Additional details
Publishing Information
- ISBN
- 0-919784-34-8
- Imprint Title
- INC93: international nuclear congress. Proceedings. V. 1,2,3
- Imprint Pagination
- [1500 p.].
- Journal Page Range
- (v.2) [8 p.].
- Report number
- INIS-mf--14809
Conference
- Title
- international nuclear congress.
- Acronym
- INC93
- Dates
- 3-6 Oct 1993.
- Place
- Toronto, ON (Canada).
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 27056926
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CANDU TYPE REACTORS; DEPTH; FRETTING CORROSION; IN-SERVICE INSPECTION; PERFORMANCE; STEAM GENERATORS; TUBES; WEAR
- Descriptors DEC
- BOILERS; CHEMICAL REACTIONS; CORROSION; DIMENSIONS; HEAVY WATER MODERATED REACTORS; INSPECTION; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS