Automated corrosion fatigue crack growth testing in pressurized water environments
- 1. Westinghouse Research and Development Center, Pittsburgh, PA (USA)
Description
This paper describes in detail a novel approach to construct a test facility for developing corrosion fatigue crack growth rate (FCGR) properties in aggressive environments. The environment studied is that of a pressurized water reactor (PWR) at 2880C (5500F) and 13.8 MPa (200 psig). To expedite data generation, each chamber was designed to accommodate two test specimens. A common water recirculation and pressurization system was employed to service two test chambers. Thus, four fatigue crack propagation rate tests could be conducted simultaneously in the pressurized water environment. The data analysis was automated to minimize the typically high labor costs associated with corrosion fatigue crack propagation testing. Verification FCGR tests conducted on an ASTM A469 rotor steel in a room temperature air environment as well as actual PWR environment FCGR tests performed on an ASTM A533 Grade B Class 2 pressure vessel steel demonstrated that the dual specimen test facility is an excellent system for developing the FCGR properties of materials in adverse environments
Additional details
Publishing Information
- Publisher
- ASTM.
- Imprint Place
- Philadelphia, PA (USA)
- ISBN
- 0-8031-0264-X
- Imprint Title
- Environment-sensitive fracture: Evaluation and comparison of test methods
- Journal Page Range
- p. 426-442.
Conference
- Title
- evaluation and comparison of test methods.
- Acronym
- ASTM symposium on environment sensitive fracture
- Dates
- 25-28 Apr 1982.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20072448
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUTOMATION; COMPUTERS; CRACK PROPAGATION; FATIGUE; FRACTURE MECHANICS; LIQUID FLOW; MECHANICAL TESTS; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR SAFETY; REACTOR VESSELS; ROTORS; STEELS; TEST FACILITIES; WATER
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CONTAINERS; ENRICHED URANIUM REACTORS; FLUID FLOW; HYDROGEN COMPOUNDS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICS; OXYGEN COMPOUNDS; POLAR SOLVENTS; POWER REACTORS; REACTORS; SAFETY; SOLVENTS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS