Effectiveness and reliability of US inservice inspection techniques

Conference · Thu Dec 31 23:00:00 EST 1981

OSTI ID:7094549

Doctor, S R; Becker, F L; Selby, G P

The work presented is from an ongoing program directed toward measuring the effectiveness and reliability of inservice inspection (ISI) of light water reactor systems (primary piping and pressure vessel). Extensive round robin and parametric evaluations have been conducted in 10 in. Sch. 80 stainless steel as well as centrifugally cast stainless steel and clad ferritic main coolant pipe welds. Results from these measurements will be viewed in relationship to US regulations and ASME Section XI Code requirements. 6 figures.

• Research Organization: Pacific Northwest Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 7094549
• Report Number(s): PNL-SA-10404; CONF-821079-2; ON: DE83002022
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
ALLOYS
CHROMIUM ALLOYS
CONTAINERS
COOLING SYSTEMS
CORROSION RESISTANT ALLOYS
CRACKS
DEFECTS
DETECTION
ENERGY SYSTEMS
IN-SERVICE INSPECTION
INSPECTION
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
PIPES
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RELIABILITY
STAINLESS STEELS
STEELS
WATER COOLED REACTORS
WELDED JOINTS