Alloy 600의 PWSCC에 미치는 열적 시효 및 삼축 응력의 영향

다국어 초록 (Multilingual Abstract)

In this study, the effects of triaxial stress was investigated in terms of primary water stress corrosion susceptibility. Thermally aged Alloy 600 specimens were prepared via accelerated heat treatment at 400 ℃ which is one of the highest temperature which will not cause the formation of excessive carbides or precipitates which will not be formed at nuclear power plant primary circuit environment. Triaxial stress was then applied by making round notch at the surface of round tensile specimen. The crack initiation time ere measured in-situ by direct current potential drop method during slow strain rate test at primary water condition. At the notched specimen, cracks were mainly observed at the region where shear stress is focused. Also, the stair shape of fracture surface was observed, which might cause by enhanced localized plasticity and multiple number of activated slip system under triaxial stress state.

목차 (Table of Contents)

• Abstract
• 1. 서론
• 2. 이론 및 실험
• 3. 결과 및 고찰
• 4. 결론
• 참고문헌