Heavy-section steel technology program. Quarterly progress report, October-December 1982. Volume 4. [PWR; BWR]

Technical Report · Sun May 01 00:00:00 EDT 1983

OSTI ID:6278426

Whitman, G D; Pugh, C E; Bryan, R H

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. A superposition solution technique for determining stress-intensity factors for semielliptical surface cracks in cylinders was implemented in pressurized thermal-shock (PTS) analyses. Subcontractors continued studies on crack arrest, cleavage fracture initiation, and cleavage transition. Specimens of the ORNL single-wire cladding were fabricated for irradiation. Pretest analyses were carried out for the upcoming thermal-shock test, TSE-7, and posttest analyses and examinations were under way for intermediate vessel test ITV-8A. Preparations for the first PTS experiment continued with design, procurement, and construction of the test facility, test vessels, and experimental apparatus.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6278426
• Report Number(s): NUREG/CR-2751-Vol.4; ORNL/TM-8369/Vol.4; ON: DE83013241
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
BWR TYPE REACTORS
PRESSURE VESSELS
REACTOR MATERIALS
PWR TYPE REACTORS
FATIGUE
FRACTURE PROPERTIES
PHYSICAL RADIATION EFFECTS
STEEL-ASTM-A508
STEEL-ASTM-A533-B
CRACKS
FUEL CANS
LEAK TESTING
SEALS
STAINLESS STEELS
STRESS ANALYSIS
TEST FACILITIES
THERMAL SHOCK
ALLOYS
CARBON STEELS
CHROMIUM ALLOYS
CONTAINERS
CORROSION RESISTANT ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
RADIATION EFFECTS
REACTORS
STEELS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
360103 - Metals & Alloys- Mechanical Properties
360106 - Metals & Alloys- Radiation Effects