Heavy-Section Steel Technology Program semiannual progress report, April-September 1984. Volume 2

Technical Report · Sat Dec 01 04:00:00 EST 1984

OSTI ID:6027357

Pugh, C E

The Heavy-Section Steel Technology (HSST) Program is conducted for the Nuclear Regulatory Commission. The studies are 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 focus is on the behavior and structural integrity of steel pressure vessels containing cracklike flaws. Starting with FY 1984, the program is organized into ten 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; and (10) pressurized-thermal-shock (PTS) technology. During this period, extensions were made to the ADINA-ORMGEN-ORVIRT fracture analysis codes to improve near-crack-tip modeling. Analytical assessments were made of laboratory specimens with potential for use in obtaining high crack-arrest toughness data. Irradiations were initiated for the study of K/sub Ic/ shifts for welds with different copper contents, and testing proceeded in the Fourth Irradiation Series. Work continued on reports covering clad-beam tests and ITV-8A that contained a low-upper-shelf weldment. Exploratory analytical fracture studies were carried out for clad cyclinders undergoing thermal-shock loadings, and fracture assessments continued for the Integrated Pressurized Thermal-Shock-Program.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6027357
• Report Number(s): NUREG/CR-3744-Vol.2; ORNL/TM-9154/V2; ON: TI85004171
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CLADDING
CONTAINERS
CONTAINMENT
CONTAINMENT SYSTEMS
COOLANT LOOPS
COOLING SYSTEMS
CRACK PROPAGATION
DEPOSITION
ENERGY SYSTEMS
ENGINEERED SAFETY SYSTEMS
FRACTURE PROPERTIES
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
MANAGEMENT
MATERIALS
MECHANICAL PROPERTIES
NATIONAL ORGANIZATIONS
ORNL
PRESSURE VESSELS
PROGRAM MANAGEMENT
REACTOR MATERIALS
REACTOR SAFETY
REACTOR VESSELS
REACTORS
SAFETY
STEELS
STRESS ANALYSIS
SURFACE COATING
SYSTEMS ANALYSIS
TESTING
THERMAL SHOCK
US AEC
US DOE
US ERDA
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS