Effectiveness of US inservice inspection techniques: a round robin test. [PWR; BWR]

Conference · Sun May 01 00:00:00 EDT 1983

OSTI ID:6217708

Doctor, S R; Heasler, P G; Selby, G P

The work presented is from an on-going program directed toward measuring the effectiveness and reliability of inservice inspection (ISI) of light water reactor systems (primary piping and pressure vessel). An extensive round robin evaluation has been conducted on cracks located in 10 inch Schedule 80 stainless steel as well as centrifugally cast stainless steel and clad ferritic main coolant pipe welds. This paper reports on the probability of detection of cracks versus crack depth for these materials and the ability to size the cracks using probe motion methods.

• Research Organization: Pacific Northwest Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 6217708
• Report Number(s): PNL-SA-11336; CONF-830562-1; ON: DE83013255
• Resource Relation: Conference: Specialist meeting on defect detection and sizing, Ispra, Italy, 3 May 1983; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
PRIMARY COOLANT CIRCUITS
PIPES
CRACKS
IN-SERVICE INSPECTION
PWR TYPE REACTORS
INTERGRANULAR CORROSION
STAINLESS STEELS
STRESS CORROSION
ALLOYS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
COOLING SYSTEMS
CORROSION
CORROSION RESISTANT ALLOYS
ENERGY SYSTEMS
INSPECTION
IRON ALLOYS
IRON BASE ALLOYS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
STEELS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled