Improved ultrasonic inspection method for stainless steel piping

Technical Report · Wed Aug 01 04:00:00 EDT 1979

DOI:https://doi.org/10.2172/5833992· OSTI ID:5833992

This report, prepared for those concerned with in-service inspection on nuclear plant piping, presents a summary of work conducted under EPRI Research Project to improve the reliability of IGSCC (intergranular stress corrosion cracking) detection by ultrasonic techniques is presented concerning nuclear plant piping in-service inspection. It consists of a brief assessment of the IGSCC incidents followed by a summary of the overall EPRI UT reliability improvement progam and abstracts of contractor-prepared design and evaluation reports. The complete reports are provided as appendixes. The transducer which resulted from this work has gained wide acceptance in nuclear plant inspection throughout the world.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (USA)
• OSTI ID: 5833992
• Report Number(s): EPRI-NP-1153
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
36 MATERIALS SCIENCE
360105* -- Metals & Alloys-- Corrosion & Erosion
42 ENGINEERING
420500 -- Engineering-- Materials Testing
440300 -- Miscellaneous Instruments-- (-1989)
47 OTHER INSTRUMENTATION
ACOUSTIC TESTING
ALLOYS
AUSTENITIC STEELS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION
CORROSION RESISTANT ALLOYS
DESIGN
ECCS
ENGINEERED SAFETY SYSTEMS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IN-SERVICE INSPECTION
INSPECTION
INTERGRANULAR CORROSION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS TESTING
NICKEL ALLOYS
NONDESTRUCTIVE TESTING
PIPELINES
REACTOR PROTECTION SYSTEMS
REACTORS
RELIABILITY
STAINLESS STEEL-304
STAINLESS STEELS
STEELS
STRESS CORROSION
TESTING
TRANSDUCERS
ULTRASONIC TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS