Published May 1983
| Version v1
Report
Crack growth resistance of low alloy steel in high temperature oxygenated water
Creators
Description
Crack growth rates for Low Alloy Steel in high temperature, high purity oxygenated water were studied under cyclic loading conditions. Both fracture mechanics and simulated reactor pressure vessel nozzle test specimens were utilized. Cycle frequency, mean stress, and coolant oxygen content were studied. The role of crack face oxidation in mitigating crack growth rates was identified. The overall data band is similar to that reported in the literature for Pressurized Water Reactor conditions. The overall impact of the study is that disposition of indications potentially found by future in-service inspections can be made with improved confidence since the resistance to crack extension is quite high
Additional details
Publishing Information
- Imprint Title
- Proceedings of the International Atomic Energy Agency specialists' meeting on subcritical crack growth. Sessions I and II. Vol. 1
- Journal Page Range
- p. 141-178.
- Report number
- NUREG/CP--0044-Vol.1
Conference
- Title
- International Atomic Energy Agency specialists' meeting on subcritical crack growth.
- Dates
- 13-15 May 1981.
- Place
- Freiburg (Germany, F.R.).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14796435
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACK PROPAGATION; NOZZLES; OXYGEN; PRESSURE VESSELS; PWR TYPE REACTORS; STEEL-ASTM-A508; STEEL-ASTM-A533; WATER; WELDED JOINTS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CONTAINERS; ELEMENTS; HYDROGEN COMPOUNDS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; NONMETALS; OXYGEN COMPOUNDS; REACTORS; STEELS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS