Heavy-section steel technology program. Quarterly progress report, October-December 1981. [PWR; BWR]

Technical Report · Thu Apr 01 04:00:00 EST 1982

OSTI ID:5342041

Whitman, G D; Bryan, R H

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. Thermal strain modifications to two- and three-dimensional fracture mechanics were checked. Subcontractors investigated fracture initiation and arrest toughness and the transition from cleavage to fibrous fracture. Investigations of properties of irradiated steel included statistical analysis of Charpy data and continued irradiation of specimens. Thermal-shock experiment TSE-6 was conducted. Welds in intermediate test vessel V-8A and testing of material characterization specimens were completed. Further analyses of pressurized thermal-shock test concepts were made. Work commenced on a study of the effects of weld overlay cladding on fracture behavior.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5342041
• Report Number(s): NUREG/CR-2141-Vol.4; ORNL/TM-8252; ON: DE82013545
• 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
ENERGY TRANSFER
FRACTURE PROPERTIES
HEAT TRANSFER
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
PRESSURE VESSELS
PWR TYPE REACTORS
REACTORS
RESEARCH PROGRAMS
STEELS
STRESSES
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS