Chemical composition and RT[sub NDT] determinations for Midland weld WF-70
- Oak Ridge National Lab., TN (United States)
The Heavy-Section Steal Irradiation Program Tenth Irradiation Series has the objective to investigate the affects of radiation on the fracture toughness of the low-upper-shelf submerged-arc welds (B W designation WF-70) in the reactor pressure vessel of the canceled Midland Unit 1 nuclear plant. This report discusses determination of variations in chemical composition And reference temperature (RT[sub NDT]) throughout the welds. Specimens were machined from different sections and through thickness locations in both the beltline and nozzle course welds. The nil-ductility transition temperatures ranged from [minus]40 to [minus]60[degrees]C ([minus]40 and [minus]76[degrees]F) while the RT[sub NDT]S, controlled by the Charpy behavior, varied from [minus]20 to 37[degrees]C ([minus]4 to 99[degrees]F). The upper-shelf energies varied from 77 to 108 J (57 to 80 ft-lb). The combined data revealed a mean 41-J (30-ft-lb) temperature of [minus]8[degrees]C (17[degrees]F) with a mean upper-shelf energy of 88 J (65 ft-lb). The copper contents range from 0.21 to 0.34 wt % in the beltline weld and from 0.37 to 0.46 wt % in the nozzle course weld. Atom probe field ion microscope analyses indicated substantial depletion of copper in the matrix but no evidence of copper clustering. Statistical analyses of the Charpy and chemical composition results as well as interpretation of the ASME procedures for RT[sub NDT] determination are discussed.
- Research Organization:
- US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering; Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6809313
- Report Number(s):
- NUREG/CR-5914; ORNL-6740; ON: TI93006316
- Country of Publication:
- United States
- Language:
- English
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36 MATERIALS SCIENCE
REACTOR VESSELS
WELDED JOINTS
FRACTURE PROPERTIES
RADIATION EFFECTS
CHARPY TEST
CHEMICAL ANALYSIS
CHEMICAL COMPOSITION
COPPER ADDITIONS
DUCTILITY
MIDLAND-1 REACTOR
RESEARCH PROGRAMS
STATISTICAL DATA
STATISTICAL MODELS
STEELS
TRANSITION TEMPERATURE
ALLOYS
CONTAINERS
COPPER ALLOYS
DATA
DESTRUCTIVE TESTING
ENRICHED URANIUM REACTORS
IMPACT TESTS
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IRON ALLOYS
IRON BASE ALLOYS
JOINTS
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MATHEMATICAL MODELS
MECHANICAL PROPERTIES
MECHANICAL TESTS
NUMERICAL DATA
PHYSICAL PROPERTIES
POWER REACTORS
PROCESS HEAT REACTORS
PWR TYPE REACTORS
REACTORS
TENSILE PROPERTIES
TESTING
THERMAL REACTORS
THERMODYNAMIC PROPERTIES
WATER COOLED REACTORS
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210200* - Power Reactors
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Light-Water Moderated
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360103 - Metals & Alloys- Mechanical Properties
360106 - Metals & Alloys- Radiation Effects