Heavy-Section Steel Technology Program. Quarterly progress report for July-September 1983. Vol. 3

Technical Report · Thu Mar 01 04:00:00 EST 1984

OSTI ID:7143794

Pugh, C E

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. The investigation focuses on the behavior and structural integrity of steel pressure vessels containing cracklike flaws. Current work is organized into seven tasks: (1) program administration and procurement, (2) fracture-mechanics analyses and investigations, (3) investigations of irradiated materials, (4) thermal-shock investigations, (5) pressure vessel investigations, (6) stainless steel cladding investigations, and (7) environmentally assisted crack-growth studies. Further analyses were performed to determine material parameters and pressure-temperature transients compatible with potential pressurized-thermal-shock experiments. Subcontractors continued studies on crack arrest, crack reinitiation, fracture transition, and environmentally assisted crack growth. Tensile tests were performed for irradiated specimens in the Third and Fourth Irradiation Series. Irradiation of the first two capsules containing Charpy and tensile specimens of one-wire stainless steel cladding was completed. Posttest analyses of thermal-shock experiment TSE-7 were conducted, and further properties data for the TSE-7 test material were determined. Preparations for the first pressurized-thermal-shock experiment PTSE-1 continued. At the test facility, the data acquisition system was integrated, a revised pressurization system was finalized, and vessel alignment fixtures were fabricated. The vessel being used in the shakedown test was instrumented and inserted into the facility. Flow and pressurization tests were performed at ambient temperature. Preparations are under way for tests of the heating system.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 7143794
• Report Number(s): NUREG/CR-3334-Vol.3; ORNL/TM-8787-Vol.3; ON: DE84007577
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
ALLOYS
CONTAINERS
FRACTURE MECHANICS
IRON ALLOYS
IRON BASE ALLOYS
MECHANICS
PHYSICAL RADIATION EFFECTS
POWER REACTORS
PRESSURE VESSELS
RADIATION EFFECTS
REACTORS
RESEARCH PROGRAMS
STEELS
THERMAL SHOCK
WATER COOLED REACTORS