| 1 | 288 C에서 수소가 SA508 Cl.3 압력용기강의 인장 거동에 미치는 영향 김인섭, 2003 춘계원자력학회, 2003 |
| 2 | 475C Embrittlement in High Chromium Oxide Dispersion Strengthened Steels Lee, J.S.; Kim, In Sup; Jang, Changheui; Kimura, A.; Kim, B.G.; Choo, K.N.; Choo, Y.S.; et al, 한국원자력학회 2005년도 추계학술발표회, pp.346 - 347, 한국원자력학회, 2005-10-27 |
| 3 | A Positron Annihilation Study on the Annealing Behavior of Defects in High Purity Titanium 김인섭, Proc. of the Korean Nuclear Society Autumn Meeting, 1994 |
| 4 | A study on the Improved Mechanical Properties of Nuclear Carbon Steel Piping through the Intercritical Heat Treatment. 김인섭, Korean Nuclear Society, 2000 |
| 5 | A Study on the Microscopic Fracture Characteristics of A 533B-1 Nucler Pressure Vessel Steels Kim, In Sup, International Symposium on Pressure Vessel Technology, Seoul, Korea, pp.19 - 21, 1989 |
| 6 | A Study on the Precipitation Behavior of the delta-phase in a Duplex Stainless Steel 김인섭, Fall Meeting of the Korean Institute of Metals, 1989 |
| 7 | Accoustic Emission Behavior During Stress Corrosion Crcking of Inconel 600 김인섭, Proc. of the Korean Nuclear Society Spring Meeting, pp.145 - 150, 1996 |
| 8 | Analysis of stress state in the ball indentation test of reactor pressure vessel steel 김인섭, Proceding of the 11-th Conferencs on Mechanical behaviors of Materials, pp.489 - 498, 1997 |
| 9 | Annealing Mechanism of Neutron-Irradiated Reactor Pressure Vessel Steel Weld 김인섭, Proc. of Korean Nuclear Society Autumn Meeting, Su Won, Korea, 1991 |
| 10 | Annealing of Neutron-Irradiated Linde 80 Reactor Pressure Vessel(RPV) Steel Weld Kim, In Sup, Plant Life Extension, 1992 |
| 11 | Application of SP test to evaluate embrittlement of dual phase stainless steel caused by sigma phase and neutron irradiation Lee J.S.; Kim, In Sup; Kimura A., Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04, pp.1957 - 1965, 2004-06-13 |
| 12 | Assessment of 13~19Cr Ferritic Oxide Dispersion Strengthened Steels for Fuel Cladding Applications 김인섭, Korean Nuclear Society Autumn Meeting, 2004 |
| 13 | Assessment of High Chromium Oxide Dispersion Strengthened Steels for Nuclear Applications Jang, Changheui; Kim, In Sup; Lee, J.S.; Kimura, A., EUROMAT 2005, 2005-09-20 |
| 14 | Austenete Decomposition during Cooling after the Intercritical Annealing of Dual-Phase Steels 김인섭, Proc. of the Symposium on Phase Transformation, Seoul, Korea, 1990 |
| 15 | Changes of the Texture and Anisotropic Mechanical Properties in Zircaloy-4 Fuel Cladding due to the Effect of B-Heat Treatment Kim, In Sup, Fall Meeting of the Atomic Energy Society of Japan, 1987 |
| 16 | Characteristics of Dynamic Strain Anging(DSA) in SA106GR.C Piping Steel 김인섭, Proc. of the Korean Nuclear Society Autumn Meeting, pp.771 - 776, 1995 |
| 17 | Characteristics of Strain Aging Phenomena in Nuclear Structural Grade Low Alloyed Carbon Steel with Heat Treatment 김인섭, Korean Nuclear Society, 2003 |
| 18 | Comparison of Wear Coefficients of Steam Generator Materials. 김인섭, Korean Nuclear Society, 2000 |
| 19 | Corrosion Fatigue Cracking of Low Alloy Steel in High Temperature Water Kim, In Sup, Asian Pacific Corrosion Control Conterece, 2001 |
| 20 | Cyclic deformation behavior of SA508 Gr.1a low alloy steel under low cycle fatigue loading in 310 C low oxygen-contained water Cho, Hyun-Chul; Kim, Byoung-Koo; Jang, Changheui; Kim, In Sup; Jung, Dae-Yul; Byeon, Seong-Cheol, 한국원자력학회 2005년도 춘계학술발표회, 한국원자력학회, 2005-05-26 |
| 21 | Cyclic Deformation Behavior of Type 316LN Stainless Steel under Low Cycle Fatigue Loading in 310oC Low Oxygen Water Jang, Changheui; Kim, In Sup; Cho, Hyunchul; Kim, Byoung Koo; Jung, Dae-Yul; Byeon, Seong-Cheol, 16th International Corrosion Congress, 2005-09-21 |
| 22 | Cyclic Stress Response and Fatigue Life of Type 316LN Stainless Steel in 310℃ Low Oxygen containing Water Cho, Hyun-Chul; Kim, Byoung-Koo; Jang, Changheui; Kim, In Sup; Kim, Byong-Sup; Byeon, Seong-Cheol, 한국원자력학회 2005년도 추계학술발표회, pp.354 - 355, 한국원자력학회, 2005-10-27 |
| 23 | Derivation of Yield Stress in Beta-Transformed Zircaloy-4 Nuclear Fuel Sheaths 김인섭, Spring Meeting of Korean Nuclear Society, 1988 |
| 24 | Development of Experimental Method to Simulate the Corrosion Products in the Primary System of Nuclear Power Plant 김인섭, Proceedings of the Korean Nuclear Society Spring Meeting, 2005 |
| 25 | Dynamic Aging Effect on Integrity of Nuclear Pressure Vessel Steel 김인섭, 1st Seminar on Nuclear Materials, KAERI, 1995 |
| 26 | Dynamic Strain Ageing Effect on Fracture Toughness of Vessel Steels, IAEA Technical Committee Meeting, 14-17 May 1991, Kim, In Sup, IAEA Technical Committee Meeting and Workshop, pp.14 - 17, 1991 |
| 27 | Dynamic strain aging in base weld metal of SA106 Gr.CPiping steel Kim, In Sup, TMS fall meeting, a part of materials week '97, pp.48 - 49, 1997 |
| 28 | Dynamic Strain Aging on the Leak-Before-Break Analysis in SA106Gr.C Piping Steel 김인섭, Proc. of the Korean Nuclear Society Spring Meeting, pp.193 - 198, 1996 |
| 29 | Dynamic Strain-Aging and Fracture Characteristics of Power Plant Components-Carbon Steels and Austenite Alloys 김인섭, Proc. of the Seventh Conference on Mechanical Behavior of Materials, 1993 |
| 30 | Dynamic Strain-Aging Effect on Fracture Toughness of Steel Kim, In Sup, American Nuclear Society, pp.251 - 253, 1990 |
| 31 | Effect of Austenitizing Temperature on Microstructure and Mechanical Properties of 12\% Cr Steel 김인섭, Fall Meeting of the Korean Institute of Metals, 1992 |
| 32 | Effect of Dynamic Strain Ageing on the Fracture Characteristics in SA-508 Class 3 Nuclear Pressure Vessel Steel 김인섭, Proc. Kim-KSME Joint Symposium '90 on Mechanical Behavior of Materials, Taejon, Korea, 1990 |
| 33 | Effect of dynamic strain aging on fracture toughness for main steam line piping of nuclear power plant Kim, In Sup, Proceedings of the Workshop on the integrity of Nuclear Component, pp.2 - 2, 1997 |
| 34 | Effect of dynamic strain aging on the low cycle fatigue behavior of ASME SA508 CL.3 steel for nuclear pressure vessels Kim, In Sup; Lee Byung-Ho, Proceedings of the 1994 Pressure Vessels and Piping Conference. Part 2 (of 19), v.287, pp.87 - 91, 1994-06-19 |
| 35 | Effect of Heat Treatment on Microstructure and Mechanical Properties of 12%Cr Steel, Hangzou, China Kim, In Sup, 1st Pacific Rim International Conference on Advanced Materials and Processing, pp.23 - 27, 1992 |
| 36 | Effect of Heat Treatment on the Microstructure and Mechanical Properties of 12% Cr Steel 김인섭, Proc. of the 3rd Symposium on Phase Transformation, Seoul, Korea, 1991 |
| 37 | Effect of Heat Treatment on the Microstucture Texture and Mechanical Properties of Zircaloy-4 김인섭, Fall Meeting of Korean Nuclear Society, 1989 |
| 38 | Effect of hydride morphology on fracture toughness of Russian pressure tube materials 김인섭, Proceeding of the Korean Nuclear Society Automn meeting, pp.100 -, 1997 |
| 39 | Effect of Hydride Morphology on the the fracture Toughness of Cold-worked Zr-2.5% Nb Pressure Tube 김인섭, Proc. of Korean Nuclear Society Spring Meeting, 1994 |
| 40 | Effect of Intercritical Annealing Treatment on the Fracture Toughness of SA106 Gr.C Piping Steel Kim, In Sup, International Conference on Nuclear Engineering, pp.188 - 188, 1999 |
| 41 | Effect of Intercritical Annealing Treatment on the Mechanical Properties of SA106 Gr.C Piping Steel 김인섭, '98 Autumn Meeting, Korean Nuclear Society, pp.191 - 198, 1998 |
| 42 | Effect of magnetic Field on the Corrosion Behavior in Carbon Steel Piping 김인섭, Proceedings of the Korean Nuclear Society Spring Meeting, 2002 |
| 43 | Effect of Microstructure on the Ductile Fracture of Ferrite-Martensite-Bainite Steels Kim, In Sup, Fall Meeting of TMS-AIME, Chicago, U.S.A., 1988 |
| 44 | Effect of specimen thickness on near-threshold fatigue crack growth 김인섭, Proceding of the 11th Conferencs on Mechanical behaviors of Materials, pp.307 -, 1997 |
| 45 | Effect of Specimen Thickness on Near-Threshold fatigue crack Propagation of SA106 Gr.C Nuclear Main Stream Pipe weld joints Kim, In Sup, TMS fall meeting a part of materials week '97, pp.15 - 17, 1997 |
| 46 | Effect of Strain Aging on the Deformation Behavior in SA508-Cl.3 Nuclear Pressure Vessel 김인섭, Fall Meeting of Korean Nuclear Society, 1989 |
| 47 | Effect of Temperature and Loading Rates on Fracture Properties in the Dynamic Strain Aging Region 김인섭, Proc. of the Sixth Conference on Mechanical Behavior of Materials, Seoul, 1992 |
| 48 | Effect of the specimen thickness on near-threshold fatigue crack growth 김인섭, Proceeding of the 11th Conferencs on Mechanical behavior of materials, 1997, pp.307 -, 1997 |
| 49 | Effects of (a+B) Heat Treatment on the Hydrogen Embrittlement of Zircaloy-4 김인섭, Proc. of the Korea Nuclear Society, Kori, 1992 |
| 50 | Effects of Corrosion Conditions and Cold Working on the Nodular Corrosion of Zircaloy-4 김인섭, Proc. of the Korean Nuclear Society Autumn Meeting, Seoul, 1992 |
| 51 | Effects of dynamic strain aging and hydrogen trapping behavior on fatigue crack growth of SA 508CL.3 steel in high temperature aerated water Lee S.G.; Kim, In Sup, International Conference on Hydrogen Effects on Material Behaviour and Corrosion Deformation Interactions, pp.849 - 857, 2002-09-22 |
| 52 | Effects of Dynamic Strain Aging on the Leak-Before-Break Analysis in SA106Gr.C Piping Steel Kim, In Sup, International Workshop on the Integrity of Nuclear Components, KINS 1996, 1996 |
| 53 | Effects of hydrogen on tensile properties of SA508 Cl.3 reactor pressure vessel at high temperature Kim, In Sup, Pacific Rim International Conference on Advanced Materials and Processing, pp.4121 - 4124, 2004 |
| 54 | Effects of Specimen Thickness and Microstructure on Near-Threshold Fatigue Crack Propagation in Ferritic Steels Kim, In Sup, international Conference on Structural Mechanics in Reactor Technology, pp.V-511 - V-518, 1999 |
| 55 | Effects of Test Temperatures on the Reciprocating Wear of Steam Generator Tubes Kim, In Sup, ASIATRIB 2002 International Conference, 2002 |
| 56 | Effects of Texture and Microstructure on the Mechanical Properties of Heat-Treated Zircaloy-4 Kim, In Sup, Second International Conference on Candu Fuel, Chalk River, Canada, pp.1 - 5, 1989 |
| 57 | Electrochemical Analysis of CANDU Feeder Piping Characterized by High Temperature Rotating Cylinder Electrode 김인섭, Proceedings of the Korean Nuclear Society Spring Meeting, 2004 |
| 58 | Electrochemical Analysis on Flow Accelerated Corrosion of CANDU Feeder piping at Elevated Temperature Kim, In Sup, 11th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, 2003 |
| 59 | Electrochemical Analysis on Fow-Accelerated Corrosion Behavior of SA106 Gr.C Steel in Alkaline Solution Kim, In Sup, Asian -Pacific Corrosion Control Conference, 2001 |
| 60 | Electrochemical Study on the Effect of Water Flow Rate on the Oxide Film of SA106 Gr.C Piping 김인섭, Korean Nuclear Society, 2002 |
