Heavy-section steel technology program: Semiannual progress report for October 1987--March 1988

Technical Report · Mon Aug 01 04:00:00 EDT 1988

OSTI ID:7101088

Corwin, W R

These studies relate to all areas of the the technology of materials fabricated into thick-section primary-coolant containment systems of light-water-cooled nuclear power reactors. The focus is on the behavior and structural integrity of steel pressure vessels containing cracklike flaws. Improvements were made in the computational efficiencies of fracture-analysis codes, enhancements were made in the constitutive models and inelastic fracture criteria in the dynamic-viscoplastic fracture version of the ADINA-ORMGEN-ORVIRT analysis codes at Oak Ridge National Laboratory (ORNL). Elastodynamic analyses and development work on viscoplastic fracture-analysis techniques were performed. Three new areas were begun: (1) the evaluation of possible enhanced low-temperature, low-flux irradiation embrittlement of reactor pressure vessel supports; (2) an assessment of boiling-water-reactor vessel integrity; and (3) a reevaluation of the applicability of various formulations of the J-integral in assessing relatively large amounts of crack extension. One additional wide-plate, crack-arrest test was performed. Crack-arrest and other fracture characterization data were obtained for clad-plate test materials. All irradiated Charpy V-notch and tensile testing was completed for the second phase of the the Seventh HSST Irradiation Series on cladding. Nondestructive examinations were completed on a segment of a clad pressurized-water reactor (PWR) vessel. 141 refs., 208 figs., 27 tabs.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 7101088
• Report Number(s): NUREG/CR-4219-Vol.5-No.1; ORNL/TM-9593/V5-N1; ON: TI88015348
• 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
CRYSTAL STRUCTURE
DOCUMENT TYPES
ELECTRON MICROSCOPY
ENERGY TRANSFER
FAILURES
FINITE ELEMENT METHOD
FRACTURE MECHANICS
FRACTURES
HARDNESS
HEAT TRANSFER
IRON ALLOYS
IRON BASE ALLOYS
MANAGEMENT
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICS
MICROSCOPY
MICROSTRUCTURE
NATIONAL ORGANIZATIONS
NUMERICAL SOLUTION
ORNL
PRESSURE VESSELS
PROGRAM MANAGEMENT
PROGRESS REPORT
PWR TYPE REACTORS
RADIATION EFFECTS
REACTORS
RESEARCH PROGRAMS
SCANNING ELECTRON MICROSCOPY
STEELS
STRAIN RATE
TENSILE PROPERTIES
TESTING
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS