Fracture toughness data for ferritic nuclear pressure vessel materials. Task A: Volume I. Final report
The object of the testing program was to evaluate heat-to-heat variability in fracture toughness of ferritic nuclear pressure vessel steels which are currently described by the reference toughness curve k/sub/IR relationship found in the ASME boiler and Pressure Vessel Code. Eight types of nuclear pressure vessel steels and weldments (total fifty heats) were studied. Tests performed over a range of temperature (approximately -150 F to 550 F) included tensile, drop weight-NDTT, Charpy V-notch, instrumented precracked Charpy, static and dynamic compact fracture and dynamic bend. New testing and data analysis procedures were established to deal with the dynamic fracture toughness measurements. This report presents all of the test results, the associated statistical analyses, and recommendations for establishing a statistically based K sub IR curve. (GRA)
- Research Organization:
- Effects Technology, Inc., Santa Barbara, CA (USA)
- OSTI ID:
- 7305727
- Report Number(s):
- PB-254694
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220200 -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103* -- Metals & Alloys-- Mechanical Properties
ALLOYS
BENDING
CARBON ADDITIONS
CONTAINERS
FERRITE
FRACTURE PROPERTIES
HIGH TEMPERATURE
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
LOW TEMPERATURE
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
MEDIUM TEMPERATURE
PRESSURE VESSELS
REACTOR MATERIALS
RECOMMENDATIONS
STEELS
TENSILE PROPERTIES
TESTING
WELDED JOINTS