Evaluation of steam generator tube 85-127 from Oconee 1B. Final report
Description
This project was undertaken to assess the relative roles of mechanical and chemical effects in the mechanism responsible for the damage observed near the 14th support plate elevation on tube 85-127 from Oconee Unit 1, steam generator B. Electron channeling, x-ray line broadening, hardness, and metallography were utilized to assess mechanical effects. Surface analysis techniques such as Auger electron spectroscopy, electron spectroscopy for compound analysis, secondary ion mass spectroscopy, energy dispersive x-ray analysis, and electron diffraction were used to assess chemical effects. Scanning and transmission electron microscopy were also utilized for detailed characterization of the damage surface. The analysis of mechanical effects provides conclusive evidence of mechanically induced damage
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A06/MF A01.
Files
Additional details
Publishing Information
- Imprint Pagination
- 121 p.
- Report number
- EPRI-NP--1794
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12625235
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CORROSION; INCONEL 600; INSPECTION; OCONEE-1 REACTOR; STEAM GENERATORS; TUBES
- Descriptors DEC
- ALLOYS; BOILERS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; ENRICHED URANIUM REACTORS; INCONEL ALLOYS; IRON ALLOYS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIOBIUM ALLOYS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; TRANSITION ELEMENT ALLOYS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS