Evaluation of the Fracture Characteristics with Thermal Aging on Dissimilar Welds in Reactor Coolant System

Jae Do Kwon; Seung Wan Woo; Young Hwan Choi

doi:10.4028/www.scientific.net/KEM.297-300.1691

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HomeKey Engineering MaterialsKey Engineering Materials Vols. 297-300Evaluation of the Fracture Characteristics with...

Evaluation of the Fracture Characteristics with Thermal Aging on Dissimilar Welds in Reactor Coolant System

Abstract:

A dissimilar weld zone exists between the pipe and nozzle in a primary reactor cooling system (RCS). Thermal aging is observed in cast stainless steel, CF8M used in a pipe as the RCS is exposed for a long period of time to a reactor operating temperature between 290 and 330°C. No effect is observed in low-alloy steel. SA508 cl.3 is used in a nozzle. The artificially accelerated aging specimens are prepared to maintain for a temperature of 430°C for 300, 1800, and 3600hrs, respectively. Then, various mechanical tests such as hardness, tension, impact test, are performed in virgin and aged specimens in order to determine the existence of dissimilar weld zones. The specimens for elastic-plastic fracture toughness tests are prepared for one type, where a notch is created in the heat affected zone of CF8M. From the experiments, it was found that J-integral values decrease as age increases.