Heavy-Section Steel Technology program. Quarterly progress report, July-September 1982. [PWR; BWR]
Technical Report
·
OSTI ID:6545759
Current work is organized into six tasks: (1) program administration and procurement, (2) fracture-mechanics analyses and investigations, (3) investigations of irradiated meterials, (4) thermal-shock investigations, (5) pressure vessel investigations, and (6) stainless steel cladding investigations. Comparison of two- and three-dimensional analysis of a vessel subjected to a pressurized-thermal shock (PTS) indicates that finiteness of flaws is important. Subcontractors investigated phenomena related to crack-arrest toughness and cleavage-fibrous fracture transitions. Irradiations of the Fourth HSST Irradiation Series were completed, and work commenced on additional irradiations. Overcooling accident analyses were also made. Intermedite vessel test V-8A was successfully conducted with the attainment and interruption of unstable tearing. Construction of the PTS test facility commenced. Additional clad-plate tests were conducted and planned.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6545759
- Report Number(s):
- NUREG/CR-2751-Vol.3; ORNL/TM-8369-Vol.3; ON: DE83005783
- Country of Publication:
- United States
- Language:
- English
Similar Records
Heavy-Section Steel Technology Program. Quarterly progress report, January-March 1982. [PWR; BWR]
Heavy-Section Steel Technology Program. Quarterly progress report, April-June 1982. [PWR; BWR]
Heavy-section steel technology program. Quarterly progress report, October-December 1982. Volume 4. [PWR; BWR]
Technical Report
·
Sun Aug 01 00:00:00 EDT 1982
·
OSTI ID:5338061
Heavy-Section Steel Technology Program. Quarterly progress report, April-June 1982. [PWR; BWR]
Technical Report
·
Tue Nov 30 23:00:00 EST 1982
·
OSTI ID:6587572
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
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
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ACCIDENTS
ALLOYS
BWR TYPE REACTORS
CARBON STEELS
CONTAINERS
FRACTURE PROPERTIES
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
PRESSURE GRADIENTS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
STEEL-ASTM-A533-B
STEELS
STRESS ANALYSIS
STRESSES
TEMPERATURE GRADIENTS
THERMAL SHOCK
THERMAL 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
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ACCIDENTS
ALLOYS
BWR TYPE REACTORS
CARBON STEELS
CONTAINERS
FRACTURE PROPERTIES
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
PRESSURE GRADIENTS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
STEEL-ASTM-A533-B
STEELS
STRESS ANALYSIS
STRESSES
TEMPERATURE GRADIENTS
THERMAL SHOCK
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS