Structural integrity of water reactor pressure boundary components. Progress report for period ending 29 Feb 1976

Technical Report · Thu Aug 26 04:00:00 EDT 1976

OSTI ID:7327160

Loss, F J

This report describes progress in a program to characterize the properties and performance of materials with respect to the structural integrity of light-water reactor pressure boundary components. The work is sponsored primarily by the U.S. Nuclear Regulatory Commission. Studies on dynamic fracture toughness are also being conducted on a cooperative basis by the Electric Power Research Institute (EPRI) and NRL. In addition, the work on dynamic fracture toughness is supported by the Office of Naval Research. This report describes progress in the following areas: (a) fatigue crack propagation in reactor pressure vessel steels in an air environment, (b) dynamic fracture toughness of 1-in. (25-mm) and precracked Charpy-V bend specimens under impact loading, (c) postirradiation notch ductility and properties recovery in reactor vessel steels, (d) factors contributing to variable resistance of structural steels to radiation embrittlement, and (e) the initial program plan to investigate the phenomena of warm prestress and plastic net ligament in support of thermal shock studies.

• Research Organization: Naval Research Lab., Washington, DC (USA)
• OSTI ID: 7327160
• Report Number(s): AD-A-030114; NRL-8006; NRL-NUREG-1
• Country of Publication: United States
• Language: English

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
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTORS
STEELS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS