Heavy-section steel technology program semiannual progress report for April-September 1987

Technical Report · Fri Apr 01 04:00:00 EST 1988

OSTI ID:5154874

Corwin, W R

The Heavy-Section Steel Technology (HSST) Program is conducted for the Nuclear Regulatory Commission (NCR). The studies relate to all areas of 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. The program is organized into 12 tasks: (1) program management, (2) fracture methodology and analysis, (3) material characterization and properties, (4) environmentally assisted crack-growth studies, (5) crack-arrest technology, (6) irradiation effects studies, (7) cladding evaluations, (8) intermediate vessel tests and analysis, (9) thermal-shock technology, (10) pressurized thermal-shock (PTS) technology, (11) Pressure Vessel Research Users' Facility (PVRUF), and (12) shipping cask material evaluations. During this period, extensions were made to fracture-analysis codes, including the addition of more 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 by ORNL and the Southwest Research Institute (SwRI) in support of the wideplate crack-arrest tests that are being performed by the National Bureau of Standards (NBS) for the HSST Program.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5154874
• Report Number(s): NUREG/CR-4219-Vol.4-No.2; ORNL/TM-9593-Vol.4-No.2; ON: TI88008884
• 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
360102 -- Metals & Alloys-- Structure & Phase Studies
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
ALGORITHMS
ALLOYS
BWR TYPE REACTORS
CONTAINERS
CRACK PROPAGATION
CRACKS
CRYSTAL STRUCTURE
DOCUMENT TYPES
FRACTOGRAPHY
FRACTURE MECHANICS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
MATERIALS
MATERIALS TESTING
MATHEMATICAL LOGIC
MECHANICAL PROPERTIES
MECHANICS
METALLOGRAPHY
MICROSTRUCTURE
PLATES
PRESSURE VESSELS
PROGRESS REPORT
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR MATERIALS
REACTORS
STEELS
TESTING
THERMAL SHOCK
WATER COOLED REACTORS
WATER MODERATED REACTORS