Corrosion fatigue behavior of an alloy 52-A508 weldment and low alloy steels under simulated BWR coolant conditions
- 1. Inst. of Nuclear Energy Research (INER), Chiaan Village, Lungtan, Taiwan (China)
Description
The corrosion fatigue crack growth behavior of A533, A508 low alloy steels and Inconel Alloy 52-A508 weldment under simulated BWR coolant conditions was studied. Corrosion fatigue crack growth rates of the dissimilar metal weldments were observed to increase with crack extension under the nominally constant ΔK loading mode. It can be accounted for by an increase in the tensile residual stress and a decrease in the crack closure effect with the weld depth. Corrosion fatigue crack growth rates of A533B3 and A508 cl. 3 steels were significantly affected by the steel sulfur content, loading frequency and dissolved oxygen content of the water coolant. When the steel sulfur content was decreased to a critical sulfur content, 0.005 wt%, the crack growth rates decreased remarkably. At the same sulfur level, the corrosion fatigue crack growth rates were comparable for the steel specimens in different orientations, which could be related to the rates of exposure of fresh sulfide to the water environment. By a rough estimate, the percentage of sulfides per unit fracture surface was equivalent for the steel specimens of both orientations. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 0-919784-89-5
- Imprint Title
- 13th International conference on environmental degradation of materials in nuclear power systems
- Imprint Pagination
- 388 Megabytes
- Journal Page Range
- [28 p.]
Conference
- Title
- 13. International conference on environmental degradation of materials in nuclear power systems
- Dates
- 19-23 Aug 2007
- Place
- Whistler, BC (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 39116863
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; CORROSION FATIGUE; CRACK PROPAGATION; DYNAMIC LOADS; LOW ALLOY STEELS; RESIDUAL STRESSES; STEEL-ASTM-A508; STEEL-ASTM-A533; WELDED JOINTS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; ENRICHED URANIUM REACTORS; FATIGUE; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; LOW ALLOY STEELS; MECHANICAL PROPERTIES; POWER REACTORS; REACTORS; STEELS; STRESSES; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 33 refs., 8 tabs., 24 figs.