Unirradiated material properties of Midland weld WF-70
Technical Report
·
OSTI ID:10194517
- Oak Ridge National Lab., TN (United States)
Weld metal, designated WF-70, taken from the nozzle course and beltline welds of the Midland Reactor, Unit 1, has been given a preliminary evaluation using the conventional Charpy V-notch (CVN), drop-weight (DWT), and chemical analyses. These tests indicated essentially identical fracture toughness at both locations, but there was a significant deference in copper content, nominally 0.25% versus 0.40%. Because the objective of this study was to evaluate the before-and-after irradiation properties, these are regarded as different materials. This report summarizes material characterization results and presents the results of fracture mechanics tests on the unirradiated material to establish baseline transition temperature and J-R curves. Tensile properties were also determined. Five experimental objectives to be accomplished from the testing of irradiated materials were identified. One of the more important objectives is to improve the precision of transition temperature shift and to identify any curve shape changes after irradiation, concentrating on utilizing data from small surveillance capsule size specimens.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering; Oak Ridge National Lab., TN (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 10194517
- Report Number(s):
- NUREG/CR--6249; ORNL/TM--12777; ON: TI95003010
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200
36 MATERIALS SCIENCE
360103
CHEMICAL COMPOSITION
DUCTILITY
EXPERIMENTAL DATA
FRACTURE PROPERTIES
MANGANESE STEELS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
MIDLAND-1 REACTOR
PHYSICAL RADIATION EFFECTS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
ULTIMATE STRENGTH
WELDED JOINTS
YIELD STRENGTH
210200
36 MATERIALS SCIENCE
360103
CHEMICAL COMPOSITION
DUCTILITY
EXPERIMENTAL DATA
FRACTURE PROPERTIES
MANGANESE STEELS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
MIDLAND-1 REACTOR
PHYSICAL RADIATION EFFECTS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
ULTIMATE STRENGTH
WELDED JOINTS
YIELD STRENGTH