• 대한기계학회논문집A
• /
• 제39권4호
• /
• pp.383-390
• /
• 2015

본 논문에서는 원전 배관 재료의 변형거동에 미치는 하중속도의 영향을 파악하기 위해서, SA508 Gr.1a 저합금강과 SA312 TP316 스테인리스강 배관재를 대상으로 상온과 원전 운전온도인 $316^{\circ}C$에서 다양한 변형률 속도로 인장시험을 수행하였다. 시험 결과, 상온에서는 두 배관재의 변형거동이 일반적인 하중속도 의존성을 보였다. 즉, 하중속도가 증가함에 따라 강도는 증가하고 연성은 감소하는 경향을 보였다. 그러나, $316^{\circ}C$에서는 하중속도가 증가함에 따라 SA508 Gr.1a 저합금강의 강도와 연신률이 모두 감소하였고 단면수축률은 감소 후 증가하는 비선형 거동을 보였다. SA312 TP316 스테인리스강의 강도, 연신률, 그리고 단면수축률은 하중속도에 관계없이 거의 일정한 값을 보였다. 시험 온도에 관계없이 SA508 Gr.1a 저합금강의 가공경화능력은 하중속도에 거의 영향을 받지 않았으나, SA312 TP316 스테인리스강에서는 하중속도가 증가함에 따라 가공경화능력이 감소하였다.

• 한국압력기기공학회 논문집
• /
• 제10권1호
• /
• pp.100-106
• /
• 2014

There is a growing need to introduce advanced pressure vessel steels with higher strength and toughness for the optimizatiooCn of the design and construction of longer life and larger capacity nuclear power plants. SA508 Gr.4N Ni-Cr-Mo low alloy steels have superior strength and fracture toughness, compared to SA508 Gr.3 Mn-Mo-Ni low alloy steel. Therefore, the application of SA508 Gr.4N low alloy steel could be considered to satisfy the strength and toughness required in advanced nuclear power plants. The purpose of this study is to characterize the microstructure and mechanical properties of SA508 Gr.4N low alloy steels. 1 ton ingot of SA508 Gr.4N model alloy was fabricated by vacuum induction melting followed by forging, quenching, and tempering. The predominant microstructure of the SA508 Gr.4N model alloy is tempered martensite having small packet and fine Cr-rich carbides. The yield strength at room temperature was 540MPa, and it was decreased with an increase of test temperature while DSA phenomenon occurred at around $288^{\circ}C$. Overall transition property of SA508 Gr.4N model alloy was much better than SA508 Gr.3 low alloy steel. The index temperature, $T_{41J}$, of SA508 Gr.4N model alloy was $-132^{\circ}C$ in Charpy impact tests, and reference nil-ductility transition temperature, $RT_{NDT}$ of $-105^{\circ}C$ was obtained from drop weight tests. From the fracture toughness tests performed in accordance with the ASTM standard E1921 Master curve method, the reference temperature, $T_0$ was $-147^{\circ}C$, which was improved more than $60^{\circ}C$ compared to SA508 Gr.3 low alloy steels.

• 한국압력기기공학회 논문집
• /
• 제6권1호
• /
• pp.50-56
• /
• 2010

Fatigue has been known as a major degradation mechanism of ASME class 1 components in nuclear power plants. Fatigue damage could be accelerated by combined interaction of several loads and environmental factors. However, the environmental effect is not explicitly addressed in the ASME S-N curve which is based on air at room temperature. Therefore many studies have been performed to understand the environmental effects on fatigue behavior of materials used in nuclear power plants. As a part of efforts, we performed low cycle fatigue tests under various environmental conditions and analyzed the environmental effects on the fatigue life of SA508 Gr. 1a low alloy steel by comparing with higuchi's model. Test results show that the fatigue life depends on water temperature, dissolved oxygen and strain rate. But strain rate over 0.4%/s has little effect on the fatigue life. To find the cause of different fatigue life with ANL's and higuchi's model, another test performed with different heat numbered and heat treated materials of SA508 Gr. 1a. On a metallurgical point of view, the material with bainite microstructure shows much longer fatigue life than that with ferrite/pearlite microstructure. And the characteristics of crack propagation as different microstructure seem to be the main cause of different fatigue life.