Heavy-section steel technology program quarterly progress report for April-June 1983. Volume 2. [PWR; BWR]
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. Charpy tests were performed for both irradiated and unirradiated specimens (state-of-the art welds) in the Fourth Irradiation Series. Irradiation of the first two capsules containing Charpy and tensile specimens of one-wire stainless steel cladding was begun. Thermal-shock experiment TSE-7 was conducted, and properties for the TSE-7 test material were determined. Preparations for the first pressurized-thermal-shock experiment (PTSE-1) continued. Construction of the test facility was completed; analyses of potential test histograms were performed; and fabrication of the two vessels for use in the shakedown test and the PTSE-1 was completed.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5532955
- Report Number(s):
- NUREG/CR-3334-Vol.2; ORNL/TM-8787-Vol.2; ON: DE84003981
- Country of Publication:
- United States
- Language:
- English
Similar Records
Heavy-section steel technology program. Volume 1. Quarterly progress report, January-March 1983. [PWR; BWR]
Heavy-section steel technology program. Quarterly progress report, October-December 1981. [PWR; BWR]
Related Subjects
36 MATERIALS SCIENCE
BWR TYPE REACTORS
PRESSURE VESSELS
REACTOR MATERIALS
PHYSICAL RADIATION EFFECTS
THERMAL SHOCK
PWR TYPE REACTORS
FRACTURE PROPERTIES
STEEL-ASTM-A508
STEEL-ASTM-A533-B
CRACKS
MICROSTRUCTURE
THERMAL STRESSES
ALLOYS
CARBON STEELS
CONTAINERS
CRYSTAL STRUCTURE
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
RADIATION EFFECTS
REACTORS
STEELS
STRESSES
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
360106 - Metals & Alloys- Radiation Effects
360103 - Metals & Alloys- Mechanical Properties