| 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 |
| 61 | Environmental Effects on Fatigue Life of 316 Stainless Steel in High Temperature Water Kim, In Sup, International Conference on Fatigue of Reactor Components, 2004 |
| 62 | Environmental fatigue testing of type 316 stainless steel in 310 C water Cho H.; Kim B.K.; Kim, In Sup; Oh S.J.; Jung D.Y.; Byeon S.C., 2005 ASME Pressure Vessels and Piping Conference, PVP2005, v.1, pp.165 - 169, 2005-07-17 |
| 63 | Environmentally Assisted Crack Growth Behavior of SA508 Cl.3 Pressure Vessel Steel 김인섭, '98 Spring Meeting of Korean Nuclear Sociaty, pp.154 - 159, 1998 |
| 64 | Evaluation of Embrittlement on Dual Phase Stainless Steel Caused by Sigma Phase and Neutron Irradiation 김인섭, HANARO Workshop 2004, 2004 |
| 65 | Evaluation of Irradiation Effects of 16MeV Proton-Irradiated 12Cr-1Mo-V Steel by Small Punch(SP) Tests 김인섭, Proc. of the Korean Nuclear Society, 1993 |
| 66 | Evaluation of Tensial Properties by Small-Scale Specimens 김인섭, Proc. of the Korean Nuclear Society Spring Annual Meeting, Pohang, 1994 |
| 67 | Evaluation of Thermal Embrittlement of Duplex Stainless Steel Using Small Punch Test Method 김인섭, 2nd Seminar on Nuclear Materials and Technology, KAERI, 1996 |
| 68 | Experimental Approaches on Flow Accelerated Corrosion Behavior of CANDU Feeder Piping Kim, In Sup, The 4th International Workshop on the Integrity of Nuclear Components, 2002 |
| 69 | Fatigue crack growth of SA508 Cl.3 pressure vessel steel in high-temperature argon and water environments Kim, In Sup; Lee S.O.; Cho H.C., Sixth International Conference on Computer Methods and Experimental Measurements for Surface Treatment Effects, Surface Treatment VI, v.7, pp.277 - 284, 2003-03-11 |
| 70 | Fatigue Crack Propagation Behavior in Butt Weldment of SA106Gr.C Main Steam Pipe Steel 김인섭, Proc. of the Korean Nuclear Society Spring Meeting, pp.92 - 97, 1996 |
| 71 | Fatigue Properties of Inconel 690 Steam Generator Tubing Materials 김인섭, Conference on Mechanical Behavior of Materials, pp.303 - 312, 1998 |
| 72 | Feect of Temperature Strain and Atmosphere on the Low Cycle Fatigue Behavior of ASME SA508cl.3 Forging Steel 김인섭, Proc. of the Seventh Conference on Mechanical Behavior of Materials, 1993 |
| 73 | Flow accelerated corrosion behavior of CANDU feeder piping characterized by high temperature rotating cylinder electrode Kim J.H.; Kim, In Sup; Chung H.S., Pressure Vessel and Piping Codes and Standards -2002- (2002 ASME Prssure Vessels and Piping Conference), v.439, pp.209 - 217, 2002-08-05 |
| 74 | Flow Accelerated Corrosion Behavior of Low Alloy Steel at Elevated Temperature 김인섭, Korean Nuclear Society, 2002 |
