Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author 133

Showing results 1 to 60 of 134

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, Changheuiresearcher; 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, Changheuiresearcher; 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, Changheuiresearcher; 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, Changheuiresearcher; 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, Changheuiresearcher; 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 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, Changheuiresearcher, PRICM 6: The 6th Pacific Rim International Conference on Advanced Materials and Processing, v.24-25, pp.1121 - 1124, 2007-11-05

33
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

34
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

35
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

36
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

37
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

38
Effect of Heat Treatment on the Microstucture Texture and Mechanical Properties of Zircaloy-4

김인섭, Fall Meeting of Korean Nuclear Society, 1989

39
Effect of hydride morphology on fracture toughness of Russian pressure tube materials

김인섭, Proceeding of the Korean Nuclear Society Automn meeting, pp.100 -, 1997

40
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

41
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

42
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

43
Effect of magnetic Field on the Corrosion Behavior in Carbon Steel Piping

김인섭, Proceedings of the Korean Nuclear Society Spring Meeting, 2002

44
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

45
Effect of specimen thickness on near-threshold fatigue crack growth

김인섭, Proceding of the 11th Conferencs on Mechanical behaviors of Materials, pp.307 -, 1997

46
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

47
Effect of Strain Aging on the Deformation Behavior in SA508-Cl.3 Nuclear Pressure Vessel

김인섭, Fall Meeting of Korean Nuclear Society, 1989

48
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

49
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

50
Effects of (a+B) Heat Treatment on the Hydrogen Embrittlement of Zircaloy-4

김인섭, Proc. of the Korea Nuclear Society, Kori, 1992

51
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

52
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

53
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

54
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

55
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

56
Effects of Test Temperatures on the Reciprocating Wear of Steam Generator Tubes

Kim, In Sup, ASIATRIB 2002 International Conference, 2002

57
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

58
Electrochemical Analysis of CANDU Feeder Piping Characterized by High Temperature Rotating Cylinder Electrode

김인섭, Proceedings of the Korean Nuclear Society Spring Meeting, 2004

59
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

60
Electrochemical Analysis on Fow-Accelerated Corrosion Behavior of SA106 Gr.C Steel in Alkaline Solution

Kim, In Sup, Asian -Pacific Corrosion Control Conference, 2001

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