Investigations of Irradiation-Anneal-Reirradiation (IAR) properties trends of RPV welds

Technical Report · Sun Dec 31 23:00:00 EST 1989

DOI:https://doi.org/10.2172/5191303· OSTI ID:5191303

Hawthorne, J R; Hiser, A L ^[1]

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1. Materials Engineering Associates, Inc., Lanham, MD (USA)

Notch ductility, fracture toughness and tensile property trends of two high copper content, submerged arc welds with 288{degree}C irradiation (I), 399{degree}C postirradiation annealing (IA) and 288{degree}C reirradiation (IAR) were investigated. Primary objectives included the determination of weld metal reembrittlement rate with fluence following an anneal and the influence of first cycle fluence level (high or low) on reembrittlement susceptibility. The welds were commercially made using a single lot of filler wire and two welding fluxes (Linde 80 and Linde 0091). A relatively-rapid reembrittlement of both weld types was observed with initial reirradiation; however, the reembrittlement rate decreased markedly after a reirradiation fluence of {approximately}0.3 {times} 10{sup 19} n/cm{sup 2}, E > 1 MeV. In turn, the benefit of IA procedures toward reducing total properties change with fluence was retained. The reembrittlement trend was independent of first cycle fluence level for the range investigated. Residual embrittlement after 399{degree}C-168 hour annealing, indexed by the 41-J temperature, appears independent of the pre-anneal condition (I or IAR); however, wide variability among welds in percent recovery is indicated. Trends in IAR behavior from Charpy-V specimen tests were found to be reinforced by tensile specimen and fracture toughness test findings. 27 refs., 78 figs., 14 tabs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering; Materials Engineering Associates, Inc., Lanham, MD (USA)
• Sponsoring Organization: NRC
• OSTI ID: 5191303
• Report Number(s): NUREG/CR-5492; MEA--2088; ON: TI90006164
• Country of Publication: United States
• Language: English

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AGING
ALLOYS
ANNEALING
CHARPY TEST
COMPILED DATA
CONTAINERS
COPPER ALLOYS
DATA
DESTRUCTIVE TESTING
DOCUMENT TYPES
DUCTILITY
EMBRITTLEMENT
FRACTURE MECHANICS
HEAT TREATMENTS
IMPACT TESTS
INFORMATION
INSPECTION
IRRADIATION
JOINTS
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL TESTS
MECHANICS
NUMERICAL DATA
PERFORMANCE TESTING
PRESSURE VESSELS
PROGRESS REPORT
PWR TYPE REACTORS
QUALITY ASSURANCE
RADIATION EFFECTS
REACTOR SAFETY
REACTORS
REGULATIONS
RESEARCH PROGRAMS
RISK ASSESSMENT
SAFETY
SPECIFICATIONS
TEMPERATURE EFFECTS
TENSILE PROPERTIES
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS