Heavy-Section Steel Technology Program quarterly progress report for April-June 1980

Technical Report · Wed Oct 01 04:00:00 EDT 1980

DOI:https://doi.org/10.2172/5511186· OSTI ID:5511186

Whitman, G. D.; Bryan, R. H.

The Heavy-Section Steel Technology Program is an engineering research activity conducted by the Oak Ridge National Laboratory for the Nuclear Regulatory Commission. The program comprises studies related to all areas of the technology of materials fabricated into thick-section primary-coolant containment systems of light-water-cooled nuclear power reactors. The investigation focuses on the behavior and structural integrity of steel pressure vessels containing cracklike flaws. Current work is organized into five tasks: (1) program administration and procurement, (2) fracture mechanics analyses and investigations, (3) investigations of irradiated materials, (4) thermal shock investigations, and (5) pressure vessel investigations. Nozzle-corner cracks under combined pressure and thermal loadings are being analyzed. Mechanisms of damping in crack propagation are being studied. Irradiation of the first specimens in the Fourth HSST Irradiation Series continued, and impact tests of several Charpy specimens from the previous series were completed. Heat-treatment conditions for the next thermal shock test were selected, and preparation of the test cylinder was initiated. Work was initiated to develop a low-upper-shelf seam weld for intermediate test vessel V-8A, and facility planning for pressurized thermal shock tests continued. 16 refs., 29 figs., 11 tabs.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5511186
• Report Number(s): NUREG/CR-1627; ORNL/NUREG/TM-401; ON: TI85015910
• 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
ALLOYS
BWR TYPE REACTORS
CHARPY TEST
COMPUTER CALCULATIONS
CONTAINERS
CONTAINMENT
CONTAINMENT SYSTEMS
CRACK PROPAGATION
CRACKS
DESTRUCTIVE TESTING
ENGINEERED SAFETY SYSTEMS
FRACTURE PROPERTIES
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
STEELS
STRESS INTENSITY FACTORS
TESTING
THERMAL SHOCK
WATER COOLED REACTORS
WATER MODERATED REACTORS