Zobrazeno 1 - 10
of 12
pro vyhledávání: '"Arthur F. Deardorff"'
Publikováno v:
TRANSACTIONS OF THE JAPAN SOCIETY OF MECHANICAL ENGINEERS Series A. 75:462-468
Publikováno v:
Volume 1: Codes and Standards.
Weld overlay (WOL) is one of the useful repair methods for cracked piping that has been successfully applied for piping in many nuclear power plants. In addition, ASME Boiler and Pressure Vessel Code Section XI provides a WOL method in Non-mandatory
Publikováno v:
Volume 4: Fluid-Structure Interaction.
Several instances of thermal fatigue cracking in small-diameter PWR branch lines off reactor main loop piping led to an industry program to evaluate the loading mechanisms responsible for the cracking. It was found that swirl penetration of hot react
Publikováno v:
Volume 1: Codes and Standards.
The net section plastic collapse equations currently used for piping flaw evaluation in ASME Section XI, IWB-3600 are derived based on thin shell theory assuming properties for a single material. Because of the wide use of weld overlays to repair pip
Preemptive Weld Overlays to Mitigate PWSCC Concerns in PWR Piping System Dissimilar Metal Butt Welds
Autor:
Anthony J. Giannuzzi, Marcos L. Herrera, Shu S. Tang, Arthur F. Deardorff, Peter C. Riccardella
Publikováno v:
Volume 6: Materials and Fabrication.
Primary water stress corrosion cracking (PWSCC) continues to be a concern in nickel-based alloys (Alloy 600 and the associated weld metals, Alloys 82 and 182) in pressurized water reactors (PWRs). It has caused cracking and leakage in a number of com
Publikováno v:
Pressure Vessel and Piping Codes and Standards.
The potential impact of reactor water environment on reducing the fatigue life of light water reactor (LWR) piping components has been an area of extensive research. While available data suggest a reduction in fatigue life when laboratory samples are
Publikováno v:
Pressure Vessel and Piping Codes and Standards.
In NUREG/CR-6674, a probabilistic fracture mechanics analysis was conducted to assess the effects of light water reactor environmental effects on the probability of fatigue initiation and subsequent crack growth leading to leakage and possible core d
Conference
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Conference
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