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

Showing results 89 to 132 of 132

89
Lifetime Estimation of the Nuclear Reactor Pressure Vessel on the Basis of Fracture Mechanics

김인섭, Spring Meeting of Korean Nuclear Society, 1990

90
Mechanical Properties of (a+B) Heat Treated Zircaloy-4

김인섭, Proc. of the 5th Conference on Mechanical Behaviors of Materials, Taejon, Korea, 1991

91
Mechanical Properties of SA106 Gr.C Piping Steel

Kim, In Sup, International Forgemasters Meeting, pp.151 - 162, 1997

92
Mechanisms of Flow Accelerated Corrosion in CANDU Feeder Piping

김인섭, '99 Spring Meeting of Korean Nuclear Society, pp.293 -, 1999

93
Microstructural Characteristics and Embrittlement Phenomena in Type ER309L Stainless Steel with Neutron Irradiation

김인섭, Mechanical Behaviors of Materials, 2002

94
Microstructure Formation and Mechanical Properties of Dual-Phase Steel

김인섭, Symposium on Phase Transpormation, 1994

95
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

96
Nonhomogeneous Stresses and Strains in Deformation of Multi-phase Alloys

김인섭, Third Conference on Mechanical Behaviors of Materials, Soul, Korea, 1989

97
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

98
Present Status of High Strength Low Ally Steels

김인섭, Steel Industry Seminar, The Korea Iron and Steel Association, 1981

99
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

100
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

101
SA106Gr.C 주증기 배관재의 피로균열성장에 미치는 후열처리의 영향

김인섭, 국내원전기기의 건전성평가기술 워크샵, 1996

102
Small Punch Test for the Evaluation of Thermal Aging Embrittlement of CF8 Duplex Stainless Steel

김인섭, Proc. of the Korean Nuclear Society Autumn Meeting, pp.79 - 84, 1996

103
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

104
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

105
Study on low cycle fatigue behaviors of type 316 stainless steel in 310 C water

김인섭, 한국원자력학회 2005년도 춘계학술발표회, 2005

106
Study on the environmentally assisted crack growth of reactor pressure vessel steel with fractography.

김인섭, Korean Nuclear Society, 2000

107
Study on the Simulation and Analysis on Corrosion Products of Piping Materials in NPP

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

108
Study on the Simulation and Analysis on Corrosion Products of Piping Materials in NPP

김인섭, Proceedings of the Korean Nuclear Society Spring Meeting, 2003

109
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

110
Tension Hold Time Effect on Low Cycle Fatigue of 2¨ù Cr-1Mo Steel

김인섭, Proc. of the 7th Conference on Mechanical Behaviors of Materials, 1993

111
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

112
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

113
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

114
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

115
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

116
Variational Principle for Nonhomogeneous Deformation of Two Phase Alloys

김인섭, Proc. Autumn Meeting of Korean Nuclear Society, 1990

117
WEAR BEHAVIOR OF STEAM GENERATOR TUBES IN HIGH TEMPERATURE WATER ENVIRONMENT

Kim, In Sup, CNS International Steam Generator Conference, 2002

118
X-Ray Diffraction Measurements of Ion-Irradiated Graphite

김인섭, Korean Nuclear Society Spring Meeting, 2005

119
고온고압 수화학분위기에서의 피로균열성장 속도에 미치는 여러가지 인자들의 영향

김인섭, '99 춘계학술대회, 한국원자력학회, pp.221 -, 1999

120
노치인장시편을 이용한 천이영역 파괴특성 연구

김인섭; 김석훈; 변택상; 이봉상; 홍준화, '98 추계학술발표회, 한국원자력학회, pp.218 - 225, 1998

121
모사된 LWR 수화학 조건에서의 균열성장 속도측정을 통한 국산 압력용기강의 건전성 평가

김인섭, '99 추계학술빌표회, 한국원자력학회, pp.225 -, 1999

122
소형펀치시험법에 의한 일축인장특성평가시의 문제점에 관한 고찰

김인섭, Proc. of Korean Nuclear Society Spring Meeting, 1994

123
수소화물의 파괴가 압력관 재료들의 파괴인성에 미치는 영향

김인섭; 오제용, '98 춘계학술발표회 한국원자력학회, pp.105 - 110, 1998

124
열처리가 Zr-2.5Nb 압력관재료의 지체균열전파에 미치는 영향

김인섭, Proc. of the Korean Nuclear Society Autumn Meeting, pp.765 - 770, 1995

125
온도와 하중비가 주증기 배관재 피로균열 성장거동에 미치는 영향

김인섭, '99 추계학술발표회, 한국원자력학회, pp.228 -, 1999

126
원자력급 흑연의 파괴인성 평가

김대종; 오승진; 장창희; 김인섭; 김응선; 지세환, 대한기계학회 2005년도 재료 및 파괴부문 추계학술대회 , 대한기계학회, 2005

127
원자력발전소 배관재 부식생성물 모사와 분석에 관한 연구

김인섭, 한국원자력학회 2003년도 춘계학술발표대회, 2003

128
이온조사에 따른 일축인장특성평가시의 문제점에 관한 고찰

김인섭, Proc. of the Korean Nuclear Society Spring Meeting, 1994

129
자기적 성질변화를 이용한 원자로 압력용기강의 조사효과평가

김인섭, Proc. of the Korean Nuclear Society Spring Meeting, pp.317 - 322, 1996

130
증기발생기 세관의 마모특성 연구

김인섭, Korean Nuclear Society 학술대회, 2003

131
증기발생기 전열관 재료의 마모특성 연구

김인섭, '99 한국원자력학회 추계학술발표회, pp.222 -, 1999

132
지르코늄 합금의 제조조건이 부식에 미치는 영향

김인섭, '99 한국원자력학회 춘계학술발표회, pp.236 -, 1999

Discover

Type

Open Access

Date issued

Subject

. next

rss_1.0 rss_2.0 atom_1.0