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
·
OSTI ID:6261373
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.
- Research Organization:
- Battelle Columbus Labs., OH (USA)
- OSTI ID:
- 6261373
- Report Number(s):
- NUREG/CR-0824; BMI-2026
- 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
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
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. Quarterly report, April--June 1978
Technical Report
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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
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Sun Oct 01 00:00:00 EDT 1978
·
OSTI ID:6490424
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
ALLOYS
BWR TYPE REACTORS
CONTAINERS
CRACKS
FRACTURE PROPERTIES
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MECHANICAL PROPERTIES
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
STEEL-ASTM-A508
STEEL-ASTM-A533
STEELS
TENSILE PROPERTIES
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS
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
ALLOYS
BWR TYPE REACTORS
CONTAINERS
CRACKS
FRACTURE PROPERTIES
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MECHANICAL PROPERTIES
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
STEEL-ASTM-A508
STEEL-ASTM-A533
STEELS
TENSILE PROPERTIES
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS