Heavy-section steel technology program: Semiannual progress report for April--September 1988

Technical Report · Wed Mar 01 04:00:00 EST 1989

DOI:https://doi.org/10.2172/6344625· OSTI ID:6344625

Corwin, W. R.

The Heavy-Section Steel Technology (HSST) Program is conducted for the Nuclear Regulatory Commission (NRC). 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. During this period, advances were made in the coordinated effort to develop the dynamic materials fracture data and the analytical tools required to construct improved fracture models for reactor pressure vessel (RPV) steels. Analytical efforts included examination of alternative parameters governing dynamic fracture, their corresponding constitutive models and computational implementation, as well as constraint and tunneling effects on crack-arrest calculations. Two areas of NRC topical support were continued: (1) the evaluation of enhanced low-temperature, low-flux irradiation embrittlement on the integrity of RPV supports; and (2) an overall assessment of low-upper-shelf (LUS) welds in RPVs with special emphasis on the reevaluation of the J-integral in assessing large amounts of crack extension. Crack-arrest and other fracture characterization data were obtained for clad-plate and wide-plate series 2 test materials. 133 refs., 11 figs., 6 tabs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering; Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6344625
• Report Number(s): NUREG/CR-4219-Vol.5-No.2; ORNL/TM-9593-Vol.5-No.2; ON: TI89009913
• 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
ALLOYS
BWR TYPE REACTORS
CONTAINERS
CRACK PROPAGATION
CRACKS
DOCUMENT TYPES
FRACTURE MECHANICS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
JOINTS
MATERIALS
MATERIALS TESTING
MECHANICS
PLATES
PRESSURE VESSELS
PROGRESS REPORT
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR MATERIALS
REACTORS
STEELS
TESTING
THERMAL SHOCK
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS