Published December 1981
| Version v1
Journal article
Analysis of residual stresses in girth welded type 304 stainless steel pipes
Description
Intergranular stress corrosion cracking (IGSCC) in boiling water reactor (BWR) piping is a problem for the nuclear power industry. Tensile residual stresses induced by welding are an important factor in IGSCC of Type 304 stainless steel pipes. Backlay and heat sink welding can retard IGSCC. 17 refs
Additional details
Additional titles
- Augmented title (English)
- BWR type reactors
Publishing Information
- Journal Title
- J. Mater. Energy Syst.
- Journal Volume
- 3
- Journal Issue
- 3
- Series
- J. Mater. Energy Syst.
- Journal Page Range
- 56-62
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14746815
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; S36: MATERIALS SCIENCE;
- Descriptors DEI
- BWR TYPE REACTORS; CRACKS; FINITE ELEMENT METHOD; INTERGRANULAR CORROSION; NUCLEAR POWER PLANTS; PIPES; RESIDUAL STRESSES; STAINLESS STEEL-304; STRESS CORROSION; TENSILE PROPERTIES; WELDED JOINTS; WELDING
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-NICKEL STEELS; CORROSION; CORROSION RESISTANT ALLOYS; FABRICATION; HEAT RESISTING ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; JOINING; JOINTS; MECHANICAL PROPERTIES; NICKEL ALLOYS; NUCLEAR FACILITIES; NUMERICAL SOLUTION; POWER PLANTS; REACTORS; STAINLESS STEELS; STEELS; STRESSES; THERMAL POWER PLANTS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS