Published May 1980
| Version v1
Report
Measured residual stresses in type 304 stainless steel piping butt weldments
Description
Residual-stress measurements on Type 304 stainless steel Schedule 80 4-, 10-, and 26-in. pipe weldments are presented. Both strain-gauge and x-ray diffraction techniques have been used. The bulk of the measurements have been made on the inner surface, since these stress levels presumably control the initiation of intergranular stress-corrosion cracking. Complete stress profiles have also been obtained through the thickness of the pipe wall, since the throughwall distribution controls the growth of a crack once it has initiated
Additional details
Additional titles
- Augmented title (English)
- BWR
Publishing Information
- Imprint Title
- Seminar on countermeasures for pipe cracking in BWRs
- Journal Page Range
- p. 23p, Paper 22.
- Report number
- EPRI-WS--79-174-Vol.2
Conference
- Title
- Seminar on countermeasures for pipe cracking in BWRs.
- Dates
- 22 - 24 Jan 1980.
- Place
- Palo Alto, CA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 13648248
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CRACKS; PERFORMANCE TESTING; PIPES; PRIMARY COOLANT CIRCUITS; REACTOR MATERIALS; RESIDUAL STRESSES; STAINLESS STEEL-304; STRESS CORROSION; WELDED JOINTS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-NICKEL STEELS; COOLING SYSTEMS; CORROSION; CORROSION RESISTANT ALLOYS; HEAT RESISTING ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; NICKEL ALLOYS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STAINLESS STEELS; STEELS; STRESSES; TESTING; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS