Thermal aging capsule results from Oconee Nuclear Station - Unit 1
Conference
·
· Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)
OSTI ID:6278260
At the Oconee Nuclear Station - Unit 1 a thermal aging capsule was removed and tested at the same time a second reactor vessel surveillance capsule was removed for testing. The thermal aging capsule had received a thermal exposure of 15,000 at 580 /sup 0/F (305/sup 0/C) and the irradiated capsule had received an exposure of 1.5 x 10/sup 18/n/cm/sup 2/. The capsule contained Charpy V-notch and tension specimens of SA-302 B modified base and weld metal and SA-533 B1 correlation monitor material. The SA-302 B base metal exhibited no significant changes in Charpy V-notch impact properties as a result of thermal aging. The heat-affected-zone data indicated a drop in upper shelf properties. This drop was attributed to limited thermal aged data points and large scatter in the base data, since the notch lateral expansion and shear fracture data did not indicate the same trend. The SA-302 B weld metal exhibited a slight increase in upper shelf energy, and the SA-533 B1 correlation material exhibited a slight decrease in upper shelf energy. No tension data are reported. The conclusions of this study agree with the results reported from the Big Rock Point reactor.
- Research Organization:
- Babcock and Wilcox Company, Lynchburg, VA
- OSTI ID:
- 6278260
- Report Number(s):
- CONF-8110312-
- Conference Information:
- Journal Name: Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States) Journal Volume: STP-819
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
CHARPY TEST
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DESTRUCTIVE TESTING
ENRICHED URANIUM REACTORS
HEAT AFFECTED ZONE
HIGH TEMPERATURE
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION CAPSULES
JOINTS
MATERIALS TESTING
MECHANICAL TESTS
NICKEL ALLOYS
OCONEE-1 REACTOR
POWER REACTORS
PWR TYPE REACTORS
REACTORS
STAINLESS STEEL-302
STAINLESS STEELS
STEELS
TEMPERATURE EFFECTS
TESTING
THERMAL DEGRADATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS
ZONES
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
CHARPY TEST
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DESTRUCTIVE TESTING
ENRICHED URANIUM REACTORS
HEAT AFFECTED ZONE
HIGH TEMPERATURE
IMPACT TESTS
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION CAPSULES
JOINTS
MATERIALS TESTING
MECHANICAL TESTS
NICKEL ALLOYS
OCONEE-1 REACTOR
POWER REACTORS
PWR TYPE REACTORS
REACTORS
STAINLESS STEEL-302
STAINLESS STEELS
STEELS
TEMPERATURE EFFECTS
TESTING
THERMAL DEGRADATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS
ZONES