Critical experiments, measurements, and analyses to establish a crack arrest methodology for nuclear pressure vessel steels
Technical Report
·
OSTI ID:6490424
Results of a program seeking (i) dynamic analyses of crack arrest in thermally stressed nuclear pressure vessels, (ii) standardization of a laboratory test method for measuring the crack arrest toughness, and (iii) a crack arrest toughness data base for unirradiated and irradiated nuclear steels and weldments are described. Dynamic finite difference analyses of fast fracture and arrest of an axial, part-through crack in a thick walled cylinder are refined and applied to the Oak Ridge National Laboratories Thermal Shock Experiment TSE-4. The influences of the mesh size and aspect ratio on the static stress intensity values are examined and the results compared with finite element calculations. A large body of crack arrest toughness (K/sub Im/) measurements on unirradiated A533B plate, A508 forging material and a submerged arc weldment are presented. The measurements were performed at temperatures in the range from the RT/sub NDT/ to RT/sub NDT + 100 C.
- Research Organization:
- Battelle Columbus Labs., OH (USA)
- OSTI ID:
- 6490424
- Report Number(s):
- NUREG/CR-0518; BMI-2010
- Country of Publication:
- United States
- Language:
- English
Similar Records
Critical experiments, measurements and analyses to establish a crack arrest methodology for nuclear pressure vessel steels. Quarterly report, April--June 1978
Critical experiments, measurements and analyses to establish a crack arrest methodology for nuclear pressure vessel steels
Critical experiments, measurements and analyses to establish a crack arrest methodology for nuclear pressure vessel steels. Seventeenth quarterly report, October--December 1978. [PWR; BWR]
Technical Report
·
Sun Dec 31 23:00:00 EST 1978
·
OSTI ID:6322724
Critical experiments, measurements and analyses to establish a crack arrest methodology for nuclear pressure vessel steels
Technical Report
·
Sat Mar 31 23:00:00 EST 1979
·
OSTI ID:6207602
Critical experiments, measurements and analyses to establish a crack arrest methodology for nuclear pressure vessel steels. Seventeenth quarterly report, October--December 1978. [PWR; BWR]
Technical Report
·
Sat Dec 31 23:00:00 EST 1977
·
OSTI ID:6261373
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360103* -- Metals & Alloys-- Mechanical Properties
ACCIDENTS
ALLOYS
BWR TYPE REACTORS
CONTAINERS
CRACKS
FRACTURE PROPERTIES
IRON ALLOYS
IRON BASE ALLOYS
LOSS OF COOLANT
MECHANICAL PROPERTIES
PERFORMANCE TESTING
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR MATERIALS
REACTORS
STEEL-ASTM-A508
STEEL-ASTM-A533
STEELS
STRESSES
TESTING
THERMAL SHOCK
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
36 MATERIALS SCIENCE
360103* -- Metals & Alloys-- Mechanical Properties
ACCIDENTS
ALLOYS
BWR TYPE REACTORS
CONTAINERS
CRACKS
FRACTURE PROPERTIES
IRON ALLOYS
IRON BASE ALLOYS
LOSS OF COOLANT
MECHANICAL PROPERTIES
PERFORMANCE TESTING
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR MATERIALS
REACTORS
STEEL-ASTM-A508
STEEL-ASTM-A533
STEELS
STRESSES
TESTING
THERMAL SHOCK
WATER COOLED REACTORS
WATER MODERATED REACTORS