Published 1984
| Version v1
Report
Analysis of defects in the cladding of a reactor pressure vessel
Description
In this paper a brief summary of the inspection and analysis of the welded cladding of the Lo2 RPV is maid. The NDT-methods, metallographic inspection and type of defects found in the cladding are described. Further the crack growth analysis and parameters used in calculations are presented. Finally the repair criteria for the subsurface defects are explained. (author)
Additional details
Publishing Information
- ISBN
- 951-38-1984-1
- Imprint Title
- Corrosion and stress corrosion of steel pressure boundary components and steam turbines
- Imprint Pagination
- 413 p.
- Journal Page Range
- p. 287-297.
- Report number
- VTT-SYMP--43
Conference
- Title
- International Atomic Energy Agency Specialist' meeting on corrosion and stress corrosion of pressure boundary components and steam turbines.
- Dates
- 22-24 Nov 1983.
- Place
- Espoo (Finland).
INIS
- Country of Publication
- Finland
- Country of Input or Organization
- Finland
- INIS RN
- 17054256
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLADDING; CRACK PROPAGATION; DEFECTS; FATIGUE; LOVIISA-2 REACTOR; METALLOGRAPHY; NONDESTRUCTIVE TESTING; PRESSURE VESSELS; SURFACES
- Descriptors DEC
- CONTAINERS; DEPOSITION; ENRICHED URANIUM REACTORS; MATERIALS TESTING; MECHANICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SURFACE COATING; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS