• Proceedings of the KSME Conference
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• 2003.04a
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• pp.131-136
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• 2003

CF8M cast austenitic stainless steel is used for several components such as primary coolant piping, elbow, pump casing, and valve bodies in light water reactors. These components are subject to thermal aging at the reactor operating temperature. Thermal aging results in spinodal decomposition of the delta-ferrite leading to increased strength and decreased toughness. In this study, three kinds of the aged CF8M specimen were prepared using an artificially simulated aging method. The objective of this study is to summarize the method of estimating ferrite contents, Charpy impact energy and J-R curve, and to evaluate the thermal embrittlement of the CF8M cast austenitic stainless steel piping used in the domestic nuclear power plants.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.15 no.2
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• pp.9-18
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• 2019

The objective of this study is to investigate the feasibility of simulating the mechanical properties of irradiatied austenitic stainless steels by cold-working. In this study, the tensile properties, cyclic hardening behaviors and fracture toughness of cold-worked TP316L stainless steel were compared with those of austenitic stainless steels irradiated by neutrons. It showed that cold-working can properly simulate the increase in strength and the decrease in ductility and fracture resistance of austenitic stainless steels by neutron irradiation, even though it could not perfectly simulate the microstructures of irradiated austenitic stainless steels. Also, cold-working can appropriately simulate the hardening behaviors of neutron irradiated austenitic stainless steels under monotonic and cyclic loading conditions.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05a
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• pp.784-789
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• 1995

핵융합로 제1벽재로서 주목받고 있는 저방사화 Fe-Cr-Mn-W계 오스테나이트 스테인리스강에 소량의 V을 첨가하고 그 기본 조성에 시그마상의 생성억제와 합금의 고온강도 향상에 효과가 있는 질소함량을 변화시켜 전보에서 보고한 소둔열처리의 영향에 이어 미세 조직 특성 및 부식 저항성에 미치는 시효열처리의 영향을 살펴보았다. 부식저항성 평가를 위해서는 양극분극시험, 침지시험 수소취성 시험을 행하였으며, 석출상의 생성양상을 살펴보기 위해서는 광학현미경 관찰, 자성측정, EPR시험 및 경도시험을 행하였다. 시험결과, 질소의 함량이 증가할수록 시그마상의 석출이 억제되는 것을 알 수 있었으며, 시효시 실험합금의 부식저항성은 주로 $600^{\circ}C$부근에서 오스테나이트상의 입계에 석출하는 크롬탄화물과 50$0^{\circ}C$부터 비교적 넓은 온도 구간에 걸쳐 페라이트상으로부터 석출 변태되는 시그마상에 의해 지배되고 있음을 알 수 있었다.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05b
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• pp.591-596
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• 1995

핵융합로 제1벽재로서 주목받고 있는 저방사화 Cr-Mn-W계 오스테나이트 스테인리스강에 소량의 V을 첨가하고 그 기본 조성에 시그마상의 생성억제와 합금의 고온강도 향상에 효과가 있는 질소함량을 변화시켜 미세 조직 특성 및 부식 저항성에 미치는 영향을 살펴보았다. 질소함량의 변화에 의한 영향과 더불어 소둔열처리 온도의 영향도 살펴보았다. 부식저항성 평가를 위해서는 양극분극시험, 침지시험, Huey시험을 행하였으며, 기계적 성질 평가를 위해서는 경도시험 및 인장 시험을 행하였다 그 결과 질소량이 증가할수록 오스테나이트상이 안정화되어 그 양이 증가하며 고용강화에 의해 경도치도 함께 증가함을 알 수 있었다 경도치는 또한 소둔온도가 증가함에 의해 감소함을 알 수 있었다. 한편 소둔온도가 증가할수록 페라이트량이 증가함을 확인하였다. 부식저항성은 질소량이 증가할수록 소둔온도가 증가할수록 향상됨을 알 수 있었다.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.19 no.2
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• pp.171-178
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• 2023

For the phase boundary crack found in the gasket made of cast austenitic stainless steel in the nuclear power plant, the oxide layers were analyzed through SEM and TEM. The results showed that cracks initiated and propagated along the austenite/δ-ferrite phase boundary, the propagation path was changed to penetrate the inside of the phase. The oxide layer located at the periphery of the crack along the phase boundary was identified as a complex multi-layered spinel structure, and Cr-rich carbides were also detected in the oxide. The cracks that propagated inside the austenite matrix were attributed to the presence of high external stresses and impurities.

• Proceedings of the Korean Institute of Surface Engineering Conference
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• 2000.05a
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• pp.9-10
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• 2000

• Proceedings of the Korean Institute of Surface Engineering Conference
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• 1999.10a
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• pp.86-86
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• 1999

• Proceedings of the Korean Institute of Surface Engineering Conference
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• 1999.05a
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• pp.118-118
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• 1999

• Journal of Welding and Joining
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• v.16 no.3
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• pp.111-120
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• 1998

To predict and evaluate metallurgical and mechanical behavior of th welds, it is essential to understand solidification behavior and microstructural evolution experienced in the welds, neither of which follows the equilibrium phase diagram because of rapid heating and cooling conditions. Metallurgical phenomena in austenitic stainless steel fusion welds, types 304, 309S, 316L, 321 and 304N, were investigated in this study. Autogenous GTA welding was performed on weld coupons, and primary solidification mode and phase distribution were investigated from the welds. Varestraint test was employed to evaluate solidification cracking susceptibilities of the alloys. GTA weld fusion zones in type 304, 321 and 304N stainless steels experienced primary ferrite solidification while those in type 309S primary austenite solidification. Type 316L exhibited a mixed type of primary ferrite and primary austenite solidification. The primary solidification mode strongly depended on $Cr_{eq}/Ni_{eq}$ ratio. In terms of solidification cracking susceptibility, type 309S that solidified as primary austenite exhibited high cracking susceptibility while the alloys experienced primary ferrite solidification showed low cracking susceptibility. The relative ranking in solidification cracking susceptibility was type 304=type 304N < type 321 < type 316L < type 309S.

• Proceedings of the KWS Conference
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• 1999.10a
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• pp.263-266
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• 1999