Fracture toughness data for ferritic nuclear-pressure-vessel materials. Task B. Laboratory testing. Final report
A comprehensive testing program on production heats of ferritic nuclear pressure vessel steel has recently been completed by Effects Technology, Inc. (ETI), and the results from this program are documented. Mechanical tests performed include tensile, drop weight NDTT, Charpy V-notch, instrumented precracked Charpy, static and dynamic compact fracture, and dynamic three-point bend; the temperature range of -150/sup 0/F to +550/sup 0/F was investigated for nine heats of A533B-1 steel, two shielded metal arc weldments (weld metal and heat-affected-zone), and an older A302B steel (ASTM correlation heat). The fracture mechanics tests were performed on specimens up to four inches thick and loading rates ranged from quasi-static to dynamic rates of 5 x 10/sup 5/ ksi-in/sup 1/2//s.
- Research Organization:
- Effects Technology, Inc., Santa Barbara, CA (USA)
- OSTI ID:
- 6082906
- Report Number(s):
- EPRI-NP-119; ON: DE82900201
- 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
CARBON STEELS
CONTAINERS
DATA
DATA COMPILATION
FRACTURE PROPERTIES
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUMERICAL DATA
PERFORMANCE TESTING
POWER PLANTS
PRESSURE VESSELS
REACTOR MATERIALS
STEEL-ASTM-A302
STEEL-ASTM-A533-B
STEELS
TESTING
THERMAL POWER PLANTS