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

• Journal of the Korean Society for Nondestructive Testing
• /
• v.26 no.1
• /
• pp.30-39
• /
• 2006

Feasibility is studied for an application of the mass-spring lattice model (MSLM), a numerical model previously developed for unidirectional composites, to the numerical simulation of ultrasonic inspection of austenitic welds modeled as transversely isotropic. Fundamental wave processes, such as propagation, reflection, refraction, and diffraction of ultrasonic waves in such an inspection are simulated using the MSLM. All numerical results show excellent agreement with the analytical results. Further, a simplified model of austenitic weld inspection has been successfully simulated using the MSLM. In conclusion, a great potential of the MSLM in numerically simulating ultrasonic inspections of austenitic welds has been manifested in this work, though significant further efforts will be required to develop a model with field practicality.

• Proceedings of the Korea Committee for Ocean Resources and Engineering Conference
• /
• 2000.10a
• /
• pp.236-239
• /
• 2000

It is important to evaluate austenitic heat resistant stainless steel because of low weldability of austenitic heat resistant stainless steel containing high Si. This study took varestraint test for evaluation of solidification cracking sensitivity and Erichsen test for evaluation of weld metal ductility. As a result of tests, solidification crack sensitivity increased with adding $N_2$ to shielding gas, and W had detrimental effect on crack resistance, but Ce had beneficial effect on crack resistance. Under same heat input, ductility of weld metal increased with welding speed.

• Journal of the Korean Society for Heat Treatment
• /
• v.23 no.3
• /
• pp.142-149
• /
• 2010

Austenitic stainless steel is more or less difficult with conventional gas nitriding treatment, but it can be nitrided after appropriate pre-heat treatment. The pretreatment was more effective upon nitriding for austenitic stainless steel than martensitic stainless steel. Both thickness and microhardness measurements indicated that effect of the nitriding treatment was more sensitive in austenitic stainless steel than martensitic stainless steel with nitriding time. Fatigue strength was most increased with SACM 645 steel among three steels.

• Corrosion Science and Technology
• /
• v.7 no.6
• /
• pp.338-343
• /
• 2008

The electrochemical properties of W-modified austenitic stainless steels containing Ta and La were evaluated in a $H_{3}PO_{4}$ type PEMFC environment. Electrochemical test was conducted in 0.05 M $H_{3}PO_{4}$ solution at $80^{\circ}C$ and electrical property was conducted by contact resistance test. XPS was conducted to analyze the chemical elements consisting of passive film. Addition of La and Ta in W-modified austenitic stainless steel shows not only better corrosion resistance but also better electrical property.

• Proceedings of the KSME Conference
• /
• 2004.04a
• /
• pp.96-101
• /
• 2004

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 embrittlement at the reactor operating temperature. The objective of this study is to summarize the method of estimating ferrite content, Charpy impact energy and J-R curve and to evaluate the thermal embrittlement of the cast austenitic stainless steel piping used in the domestic nuclear power plants. The result of evaluation, two domestic nuclear power plants used CF-8M and CF-8A material has adequate fracture toughness after saturation.

• Corrosion Science and Technology
• /
• v.5 no.5
• /
• pp.153-159
• /
• 2006

Austenitic stainless steels with addition of various amounts of Mo and W were evaluated in terms of corrosion and contact resistance to determine optimum alloy composition of metallic bipolar plate for PEMFC. The corrosion property was evaluated by both acid fume exposure test at $130^{\circ}C$ and by electrochemical polarization tests in $H_3PO_4$ solution at $80^{\circ}C$. Austenitic stainless steel with proper amount of Mo and W demonstrated not only good corrosion resistance but also low contact resistance. Analyses on the passive film show that partial substitution of Mo by W enhances passive film stability and repassivation property. Test results suggest that austenitic stainless steel with 2 wt%Mo and 4 wt%W has optimum composition for metallic bipolar plate used in PEMFC.

• Steel and Composite Structures
• /
• v.47 no.1
• /
• pp.135-145
• /
• 2023

This study presents a numerical investigation into the hysteretic behavior of cold-formed austenitic stainless steel square hollow section (SHS) brace members using a commercial finite element (FE) analysis software ABAQUS/Standard. The initial/post buckling and fracture life of SHS brace members are comprehensively investigated through parametric studies with FE models incorporating ductile fracture model, which is validated against the existing laboratory test results collected from the literature. It is found that the current predictive models are applicable for the initial buckling strengths of SHS brace members under cyclic loading, while result in significant inaccuracy in predictions for the post-buckling strength and fracture life. The modified predictive model is therefore proposed and the applicability was then confirmed through excellent comparisons with test results for cold-formed austenitic stainless SHS brace members.

• Proceedings of the KWS Conference
• /
• 1993.05a
• /
• pp.68-69
• /
• 1993

• Proceedings of the KWS Conference
• /
• 2001.05a
• /
• pp.248-251
• /
• 2001