Published June 1986
| Version v1
Report
Evaluation of the toughness of austenitic stainless steel pipe weldments. Final report
Description
The strength of stainless steel weldments in nuclear piping systems is typically chosen larger than that of the base piping material to address welding uncertainties. Associated with this higher strength one often finds a degradation in fracture toughness and reduced ability to support load in the presence of a weldment crack. In this research, typical nuclear piping flux welds were tested to determine if their load-carrying ability was consistent with ASME flaw acceptance criteria. Fracture behavior, tensile properties, and Charpy toughness were evaluated at LWR operating temperatures. The measured toughness was well above the minimum value assumed in the Section XI flaw acceptance criteria for austenitic flux weldments. 16 refs., 51 figs
Availability note (English)
Research Reports Center, Box 50490, Palo Alto, CA 94303.Additional details
Publishing Information
- Imprint Pagination
- 82 p.
- Report number
- EPRI-NP--4668
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17073610
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- ALGORITHMS; AUSTENITIC STEELS; BWR TYPE REACTORS; EVALUATION; FRACTURE MECHANICS; FRACTURES; MATERIALS TESTING; PIPES; PWR TYPE REACTORS; STAINLESS STEELS; WELDED JOINTS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; ENRICHED URANIUM REACTORS; FAILURES; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; MECHANICS; POWER REACTORS; REACTORS; STEELS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS