Browse "NE-Conference Papers(학술회의논문)" by Author Kim, In Sup
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| 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 |
| 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 |
| Annealing of Neutron-Irradiated Linde 80 Reactor Pressure Vessel(RPV) Steel Weld Kim, In Sup, Plant Life Extension, 1992 |
| 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 |
| 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 |
| 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 |
| Comparative study of fatigue life of type 316LN austenitic stainless steel in 310C low oxygen-containing water with prediction models Kim, Byoung Koo; Jang, Changheui; Kim, In Sup; Kim, Byong Sup; Byeon, Seong Cheol, Korea Nuclear Society, Korea Nuclear Society, 2006 |
| Corrosion Fatigue Cracking of Low Alloy Steel in High Temperature Water Kim, In Sup, Asian Pacific Corrosion Control Conterece, 2001 |
| Corrosive Wear Test of Alloy 690 in Water Chemistry Environment at Room-temperature Hong, Seung Mo; Jang, Changheui; Lee, Sang Gyu; Kim, In Sup, Korean Nuclear Society, Korean Nuclear Society, 2006 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| Dynamic Strain-Aging Effect on Fracture Toughness of Steel Kim, In Sup, American Nuclear Society, pp.251 - 253, 1990 |
| Effect of cyclic strain rate on environmental fatigue behaviors of SA508 Gr.1a low alloy steel in 310WoC deoxygenated water Cho, H.; Jang, H.; Kim, Byung Koo; Kim, In Sup; Jang, Changheui, PRICM 6: The 6th Pacific Rim International Conference on Advanced Materials and Processing, pp.1121 - 1124, 123, 2007-11-05 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| Effects of Test Temperatures on the Reciprocating Wear of Steam Generator Tubes Kim, In Sup, ASIATRIB 2002 International Conference, 2002 |
| 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 |
| 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 |
| Electrochemical Analysis on Fow-Accelerated Corrosion Behavior of SA106 Gr.C Steel in Alkaline Solution Kim, In Sup, Asian -Pacific Corrosion Control Conference, 2001 |
| Environmental Effects on Fatigue Life of 316 Stainless Steel in High Temperature Water Kim, In Sup, International Conference on Fatigue of Reactor Components, 2004 |
| 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 |
| Environmental Fatigue Tests in the Deaerated High Temperature Water Jang, Changheui; Cho, Hyunchul; Jang, Hun; Kim, In Sup; Moon, Chan Kook, 2007 KEPIC Week, 2007 |
| 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 |
| 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 |
| 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 |
| Flow-Accelerated Corrosion Behaviour of SA106 Gr.C Steel in Alkaline Solution using Rotating Cylinder Electrode Kim, In Sup, International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, pp.1 - 10, 2001 |
| Hydrogen embrittlement of oxide dispersion strengthening steels under in-situ cathodic charging Lee J.S.; Kimura A.; Ukai S.; Fujiwara M.; Kim, In Sup, Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04, pp.2016 - 2022, 2004-06-13 |
| Impact fretting wear of Alloy 600 and Alloy 690 tubes at 290℃ Hong S.M.; Kim, In Sup; Park C.Y., American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05, v.5, pp.3029 - 3034, 2005-05-15 |
| Impact fretting wear of Alloy 690 tubes at 290 C Kim, In Sup, China International Symposium on Tribology, 2004 |
| Influence of neutron irradiation on hardening and embrittlement phenomena in reactor pressure vessel cladding material Lee J.S.; Kim, In Sup; Kasada R.; Kimura A., Thermec 2003 Processing and Manufacturing of Advanced Materials, no.5, pp.4477 - 4482, 2003-07-07 |
| Investigation of Initial Deformation Behavior during Small Punch Test Kim, In Sup, in Proc. of the Second Pacific Rim International Conference on Advanced Materials and Processing(PRICM-2), Advanced Materials and Pforcessing, ed. by K.S Shin, J.K. Yoon and S.J. Kim, The Korean Institute of Metals and Materials, pp.1235 - 1240, 1995 |
| Irradiation Embrittlement of Cladding and HAZ of RPV Steel Jang, Changheui; Kim, In Sup; Lee, J.S.; Kimura, A., International Symposium on Research Reactor and Neutron Science, 2005-04-15 |
| Mechanical Properties of SA106 Gr.C Piping Steel Kim, In Sup, International Forgemasters Meeting, pp.151 - 162, 1997 |
| Near-threshold fatigue crack growth behavior of SA106 GR.C pipe weld joint Kim, In Sup, International Welding Conference (IWC '99), pp.757 - 764, 1999 |
| Positron Annihilation Technique for the Detection of Defects in High Purity Titanium Kim, In Sup, in Proc. of the Second Pacific Rim International Conference on Advanced Materials and Processing(PRICM-2), Advanced Materials and Pforcessing, ed. by K.S Shin, J.K. Yoon and S.J. Kim, The Korean Institute of Metals and Materials, pp.1159 - 1164, 1995 |
| Reduction in fatigue life of SA508 Gr.1a low alloy steel in 310C low oxygen-containing water Cho, Hyunchul; Kim, Byoung Koo; Jang, Changheui; Kim, In Sup; Jang, Hun, 한국압력기기공학회 학술대회, 한국압력기기공학회, 2006 |
| Reduction in fatigue life of type 316LN stainless steel in 310 C low oxygen-containing water Cho, Hyun-Chul; Kim, Byoung-Koo; Jang, Changheui; Kim, In Sup; Kim, Byong-Sup; Byeon, Seong-Cheol, 한국원자력학회 2005년도 추계학술발표회, 한국원자력학회, 2005-10-27 |
| Role of Compressive Stess on Initial Deformation During Small Punch Test, Transactions of American Nuclear Society, Vol.71, 192-193, 1994 Kim, In Sup, American Nuclear Society, pp.192 - 193, 1994 |
| Strain Rate Effect on the Onset of Environmentally Assisted Crack of Pressure Vessel Steel in High Temperature Water Kim, In Sup, International Symposium on the Onset of Environmental Degradation of Materials in Nuclear Power Systems- Water Reactors, pp.11 - 20, 2001 |
| Strain rate effects on the fatigue crack growth of reactor pressure vessel steel in high temperature water environment Kim, In Sup, PVP-Vol. 409, ASME 2000, pp.161 - 168, 2000 |
| Temperature and loading rate dependence of deformation and fracture characteristics of the SA508 pressure vessel steel in the upper shelf region Kim, In Sup; Kang Sung Sik, Proceedings of the 6th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, pp.139 - 144, 1993-08-01 |
| The Effect of Subsurface Deformation on the Wear Rate of Steam Generator Tubes in Room Temperature Water Kim, In Sup, International Tribology Conference AUSTRIB '02, pp.717 - 723, 2002 |
| The Evaluation of Effect of Yield Stress on Delayed Hydride Cracking in Zr-2.5Nb Alloys Kim, In Sup, The TMS Fall Meeting '99, pp.77 - 77, 1999 |
| THE INFLUENCE OF INTERCRITICAL ANNEALING TREATMENT ON THE STRAIN AGING PHENOMENA IN SA106 GR.C PIPING STEEL Kim, In Sup, HSLA Steels '2000, pp.415 - 420, 2000 |
| Thermal Aging Embrittlement of High Chromium Oxide Dispersion Strengthening Steels Lee, J.S; Kim, In Sup; Jang, Changheui; Kimura, A.; Kim, B.G.; Choo, KN; Choo, Y.S; et al, 한국원자력학회 2005년도 춘계학술발표회, pp.471 - 472, 한국원자력학회, 2005-05-26 |
| Thermal Aging Embrittlement of High Cr Oxide Dispersion Strengthened Steels Jang, Changheui; Kim, In Sup; Lee, J.S.; Kimura, A., ICFRM-12, 2005-12-07 |
| WEAR BEHAVIOR OF STEAM GENERATOR TUBES IN HIGH TEMPERATURE WATER ENVIRONMENT Kim, In Sup, CNS International Steam Generator Conference, 2002 |
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