원자로 및 고온 재료 연구실

Paper

Total : 141

141

2010
Effects of the Helium Environment on Degradation of Nickel-Base Superalloys

U.S. Department of Energy Office of Scientific and Technical Information

CH Jang, DJ Kim, D Datta, MW Kim, JH Kwon, A Arief, JY Cho
LINK
140

2010
Diametral Creep Prediction of the Pressure Tubes in CANDU Reactors Using Fuzzy Neural Networks

IAEA | 50 years of INIS

Sung Han Lee, Young Gyu No, Man Gyun Na, Jae Yong Lee, Chang Heui Jang, Dong Hoon Kim
LINK
139

2010
Effects of Carburization and Decarburization on Mechanical Properties of Nickel-Base Superalloys

Proceeding of the 12th International Conference on Pressure Vessel Technology

D Kim, I Sah, Changheui Jang
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138

2010
The effect of material variability on low cycle fatigue resistance of low alloy steels in a 310°C deoxygenated water

714th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009

H Jang, J-D Hong, JG Lee, Changheui Jang
LINK
137

2010
Korean PMMD: Approach and Prospect

Transactions

Il Soon Hwang, Suk Chull Kang, Jun Hwa Hong, Ho Sang Shin, Changheui Jang, Young Suk Kim
LINK
136

2010
Effect of thermo-mechanical processing on microstructure and creep properties of the foils of alloy 617

Journal of nuclear materials

SK Sharma, Changheui Jang, KJ Kang
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135

2010
Oxidation characteristics and oxide layer evolution of alloy 617 and Haynes 230 at 900°C and 1100°C

Oxidation of Metals

Daejong Kim, Changheui Jang, Woo Seog Ryu
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134

2010
Diametral Compressive Strength and Elastic Modulus of Flattened Disc using Diametral Compressive Test

IAEA | 50 years of INIS

Dong Hoon Kim, Byung Jun Kim, Chang Heui Jang, Se Hwan Chi
LINK
133

2010
Environmental Fatigue Behaviors of Type 316LN Stainless Steels in Simulated PWR Water with Different Dissolved Hydrogen Contents

IAEA | 50 years of INIS

Hun Jang, Pyung Yeon Jo, Chang Heui Jang
LINK
132

2010
The Effect of Inspection Model on the Probability of Vessel Failure due to Pressurized Thermal Shock

IAEA | 50 years of INIS

Myung Jo Jhung, Young Hwan Choi, Chang Heui Jang
LINK
131

2010
Irradiation hardening and embrittlement in high-Cr oxide dispersion strengthened steels

Journal of nuclear materials

S Oh, JS Lee, Changheui Jang, A Kimura
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130

2010
Estimation of Pressure Tube Diametral Creep for CANDU Reactors Using Fuzzy Neural Networks

6th International Topical Meeting on Nuclear Plant Instrumentation Control and Human Machine Interface Technology

Changheui Jang
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129

2010
Ancient flood records from historical documents in Korea

EGUGA

HJ Kim, SJ Noh, CH Jang
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128

2010
An Assessment of the Integrity of the PWR Vessels, Second report by a study group under the chairmanship of D. W. Marshall

Journal of nuclear science and technology

Myung Jo Jhung, Young Hwan Choi, Changheui Jang
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127

2010
Format and Content of Plant-Specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactor

Journal of nuclear science and technology

Myung Jo Jhung, Young Hwan Choi, Changheui Jang
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126

2010
Failure Probability of Kori 1 Reactor Pressure Vessel for Pressurized Thermal Shock Failure Probability of Kori 1 Reactor Pressure Vessel for Pressurized Thermal Shock, 2008

Journal of nuclear science and technology

Myung Jo Jhung, Young Hwan Choi, Changheui Jang
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125

2010
Boiler and Pressure Vessel Code Boiler and Pressure Vessel Code, 2004

Journal of nuclear science and technology

Myung Jo Jhung, Young Hwan Choi, Changheui Jang
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124

2010
Reactor Probabilistic Integrity Evaluation (RPIE) Code: User's Guide Reactor Probabilistic Integrity Evaluation (RPIE) Code: User's Guide, 2008

Journal of nuclear science and technology

Myung Jo Jhung, Young Hwan Choi, Changheui Jang
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123

2010
Radiation Embrittlement of Reactor Vessel Materials Radiation Embrittlement of Reactor Vessel Materials, 1988

Journal of nuclear science and technology

Myung Jo Jhung, Young Hwan Choi, Changheui Jang
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122

2010
Structural integrity of reactor pressure vessel for small break loss of coolant accident

Journal of nuclear science and technology

Myung Jo Jhung, Young Hwan Choi, Changheui Jang
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121

2010
Current Status of Hot Steam Corrosion Evaluation of the Candidate Materials for Intermediate Heat Exchangers of HTSE System

Transactions of the Korean Society of Pressure Vessels and Piping

Minu Kim, Dong Hoon Kim, Changheui Jang, Duk-Joo Yoon
LINK
120

2010
Corrosive Wear of Alloy 690 Tubes in Alkaline Water

Corrosion Science and Technology

Seung Mo Hong, Changheui Jang, In Sup Kim
LINK
119

2010
Failure assessment of nuclear piping components due to combined degradation mechanisms by an advanced probabilistic fracture mechanics code

ASME Pressure Vessels and Piping Conference

Debashis Datta, Changheui Jang
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118

2010
Application of fracture mechanics for the integrity analysis of reactor pressure vessel

16th Pacific Basin Nuclear Conference (16PBNC)

Changheui Jang, Bong-Sang Lee
LINK
117

2010
Leak failure analysis for reactor coolant loop in a nuclear power plant

Proceedings of the 16th Pacific Basin Nuclear Conference (16PBNC), Aomori, Japan, P16P1153

Debashis Datta, Changheui Jang, Jun-Seog Yang
LINK
116

2010
Microstructural Damages of Alloy 617 under Creep Stress at Elevated Temperature

IAEA | 50 years of INIS

Daejong Kim, Changheui Jang, Wooseog Ryu
LINK
115

2010
The Effect of Heat Treatment on Mechanical Properties and Microstructures of Alloy 690

IAEA | 50 years of INIS

Pyeongyeon Jo, Hun Jang, Changheui Jang, Hyunchul Cho, Byeongwook Noh
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114

2010
Effect of niobium content on hydride embrittlement of zirconium alloys

IAEA | 50 years of INIS

Seung Jin Oh, Chang Heui Jang, Jun Hwan Kim, Yong Hwan Jeong
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113

2010
Mechanical property variation within Inconel 82/182 dissimilar metal weld between low alloy steel and 316 stainless steel

International Journal of Pressure Vessels and Piping

Changheui Jang, Jounghoon Lee, Jong Sung Kim, Tae Eun Jin
LINK
112

2010
Structural integrity assessment of reactor pressure vessels during pressurized thermal shock

Journal of mechanical science and technology

Myung Jo Jhung, Seok Hun Kim, Young Hwan Choi, Sunggyu Jung, Jong Min Kim, Ji Ho Kim, Jong Wook Kim, Changheui Jang, Yoon Suk Chang, Ki Sig Kang
LINK
111

2010
Characterisation of oxidation and oxide layers of nickel-base superalloys at high temperature

Nuclear Science Structural Materials for Innovative Nuclear Systems (SMINS) Workshop Proceedings-Karlsruhe, Germany 4-6 June 2007: Workshop Proceedings-Karlsruhe, Germany 4-6 June 2007

Changheui Jang, Daejin Lee, Daejong Kim
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110

2010
Creep behaviors of alloy 617 at temperatures between 800 and 1000℃

International Conference on Advances in Nuclear Power Plants, ICAPP 2008

Daejong Kim, Changheui Jang, WS Ryu
LINK
109

2010
Oxidation behaviour of an Alloy 617 in very high-temperature air and helium environments

International Journal of Pressure Vessels and Piping

Changheui Jang, Daejin Lee, Daejong Kim
LINK
108

2010
Effect of Cyclic Strain Rate and Sulfides on Environmentally Assisted Cracking Behaviors of SA508 GR. 1A Low Alloy Steel in Deoxygenated Water at 310℃

Nuclear Engineering and Technology

Hun Jang, HYUNCHUL Cho, CHANGHEUI Jang, Tae Soon Kim, Chan Kook Moon
LINK
107

2010
Low cycle fatigue behaviors of type 316LN austenitic stainless steel in 310° C deaerated water–fatigue life and dislocation structure development

Materials Science and Engineering: A

Hyunchul Cho, Byoung Koo Kim, In Sup Kim, Changheui Jang
LINK
106

2010
Prediction of Streamflow and the Effect of Input Parameters in Small Urban Catchments

iEMSs

HJ Kim, SJ Noh, CH Jang, YJ Lee
LINK
105

2010
A Study on the Structural Integrity Assessment of Dissimilar Welds on Nuclear Power Plant

Journal of Welding and Joining

Jong-Sung Kim, Tae-Eun Jin, Yun-Jae Kim, Chang-Heui Jang
LINK
104

2010
Feasibility of Ultrasonic Inspection for Nuclear Grade Graphite

Journal of the Korean Society for Nondestructive Testing

Jae-Seok Park, Byung-Sik Yoon, Chang-Heui Jang, Jong-Po Lee
LINK
103

2010
Creep-Environment Interactions of Alloy 617 at Elevated Temperature

ASME Pressure Vessels and Piping Conference

Daejong Kim, Changheui Jang, Woo Seog Ryu
LINK
102

2010
Creep behaviors of alloy 617 at temperatures between 800 and 1000 deg. C

Proceedings of the 2008 International Congress on Advances in Nuclear Power Plants-ICAPP'08

D Kim, C Jang, WS Ryu
LINK
101

2010
Development of Probabilistic Fracture Mechanics Code for Primary System Pipes and Application for RI-ISI

ASME Pressure Vessels and Piping Conference

Changheui Jang, Debashis Datta, Jun-Seog Yang
LINK
100

2010
Failure probability assessment of a PWR Primary System Piping Subcomponents under different loading conditions

IAEA Second International Symposium on Nuclear Power Plant Life Management, Shanghai, China

D Datta, C Jang
LINK
99

2010
Effect of Niobium on hydride embrittlement of zirconium alloys

IAEA | 50 years of INIS

Seungjin Oh, Changheui Jang, Junhwan Kim, Yonghwan Jeong
LINK
98

2010
Leak Failure Analysis of the Stainless Steel Narrow Gap Welds in Nuclear Power Plant Piping

Debashis Datta, Changheui Jang
LINK
97

2010
Environmental Effect on the Characteristics of the Structural Materials of the New Advanced Power Plant

IAEA | 50 years of INIS

Taesoon Kim, Chankook Moon, Changheui Jang, Hyunchul Cho
LINK
96

2010
Creep and Oxidation Behaviors of Alloy 617 in Air and He Environment

IAEA | 50 years of INIS

Daejong Kim, Changheui Jang, Daejin Lee, Wooseog Ryu
LINK
95

2010
Mechanical Properties Evaluation in Inconel 82/182 Dissimilar Metal Welds

IASMiRT

Jounghoon Lee, Changheui Jang, Jong Sung Kim, Tae Eun Jin
LINK
94

2010
Embrittlement and hardening during thermal aging of high Cr oxide dispersion strengthened alloys

Journal of nuclear materials

JS Lee, CH Jang, In Sup Kim, A Kimura
LINK
93

2010
ASME Boiler and Pressure Vessel Code III Division 1-Appendices ASME Boiler and Pressure Vessel Code III Division 1-Appendices, 1986

Journal of nuclear science and technology

Hyunchul Cho, Byoung Koo Kim, In Sup Kim, Changheui JANG, Dae Yul JUNG
LINK
92

2010
Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials, 2006

Journal of nuclear science and technology

Hyunchul Cho, Byoung Koo Kim, In Sup Kim, Changheui JANG, Dae Yul JUNG
LINK
91

2010
Effects of LWR Coolant Environments on Fatigue Design Curves of Austenitic Stainless Steels Effects of LWR Coolant Environments on Fatigue Design Curves of Austenitic Stainless …

Journal of nuclear science and technology

Hyunchul Cho, Byoung Koo Kim, In Sup Kim, Changheui JANG, Dae Yul JUNG
LINK
90

2010
Hydrogen Effects on Material Behavior and Corrosion Deformation Interactions Hydrogen Effects on Material Behavior and Corrosion Deformation Interactions, 2003

Journal of nuclear science and technology

Hyunchul Cho, Byoung Koo Kim, In Sup Kim, Changheui JANG, Dae Yul JUNG
LINK
89

2010
Oxidation characteristics of nickel-base superalloys at high temperature in air and helium atmospheres

U.S. Department of Energy Office of Scientific and Technical Information

Lee Daejin, Kim Daejong, Jang Changheui
LINK
88

2010
A Numerical Study on an Optimum Design of a Cross-flow Type Power Turbine (CPT)

U.S. Department of Energy Office of Scientific and Technical Information

Joung Hoon Lee, Chang Heui Jang, Jong Sung Kim, Tae Eun Jin
LINK
87

2010
Effect of alloying elements on the tensile properties of hydrided zirconium alloys

U.S. Department of Energy Office of Scientific and Technical Information

Seungjin Oh, Changheui Jang, Jun Hwan Kim, Yong Hwan Jeong
LINK
86

2010
The Cyclic Strain Rate Dependence on Environmentally Assisted Cracking Behaviors of SA508 Gr. 1a Low Alloy Steel in 310. deg. C Deoxygenated Water

U.S. Department of Energy Office of Scientific and Technical Information

Hun Jang, Hyun Chul Cho, Byoung Koo Kim, In Sup Kim, Chang Heui Jang, Byoung Koo Kim
LINK
85

2010
Fatigue life and crack growth mechanisms of the type 316LN austenitic stainless steel in 310° C deoxygenated water

Journal of nuclear science and technology

Hyunchul Cho, Byoung Koo Kim, In Sup Kim, Changheui Jang, Dae Yul Jung
LINK
84

2010
The effect of corrosion product on the corrosion resistance of the galvanized steel in NaCl solutions

ISRSM2007

Changheui Jang, SM Hong, SJ Lee, JM Kim, SH Lee
LINK
83

2010
Evaluation of Mechanical Properties in Inconel 82/182 Dissimilar Metal Welds

Proceedings of the KSME Conference

Joung-Hoon Lee, Chang-Heui Jang, Jong-Sung Kim, Tae-Eun Jin
LINK
82

2010
VLBI monitoring of OVV 1633+ 382 after mm flare-22GHz preliminary results

The Bulletin of The Korean Astronomical Society

Byeong-Won Son, T Krichbaum, SS Lee, A Witzel, A Zensus
LINK
81

2010
Part 2-IX Environmental Effects on Mechanical Behavior-Environmental Fatigue Behaviors of SA508 Gr. 1a Low Alloy Steel in 310 (degree) C Deoxygenated Water

Key Engineering Materials

HC Cho, H Jang, BK Kim, IS Kim, CH Jang
LINK
80

2010
Effect of cyclic strain rate on environmental fatigue behaviors of SA508 Gr. 1a low alloy steel in 310° C deoxygenated water

Advanced Materials Research

Hyun Chul Cho, Hun Jang, Byoung Koo Kim, In Sup Kim, Chang Heui Jang
LINK
79

2010
Environmental Fatigue Behaviors of SA508 Gr. 1a Low Alloy Steel in 310° C Deoxygenated Water

Key Engineering Materials

Hyun Chul Cho, Hun Jang, Byoung Koo Kim, In Sup Kim, Chang Heui Jang
LINK
78

2010
Environmental Fatigue Tests in the Deaerated High Temperature Water

2007 KEPIC Week

Changheui Jang, Hyunchul Cho, Hun Jang, In Sup Kim, Chan Kook Moon
LINK
77

2010
Treatment of the thermal–hydraulic uncertainties in the pressurized thermal shock analysis

Nuclear engineering and design

Changheui Jang
LINK
76

2010
The high temperature oxidation behaviors of several nickel base superalloys

2006 Winter Meeting of the American Nuclear Society

L Daejin, L Sanggyu, Changheui Jang
LINK
75

2010
Fracture toughness of IG-11 graphite with crack size measurement methods

Transactions

Daejong Kim, Changheui Jang, Se-Hwan Chi
LINK
74

2010
Study on Low Cycle Fatigue Behavior of Type 316 Stainless Steel in a 310C Water Environment

International Conference on Water Chemistry of Nuclear Reactor Systems

Changheui Jang
LINK
73

2010
Oxidation of Inconel alloy 617 at the Elevated Temperature Air Environment

Korea Nuclear Society

Daejin Lee, Sanggyu Lee, In Sup Kim, Changheui Jang
LINK
72

2010
Comparative Study of Fatigue Life of Type 316LN Austenitic Stainless Steel in 310. deg. C Low Oxygen-containing Water with Prediction Models

U.S. Department of Energy Office of Scientific and Technical Information

Hyun Chul Cho, Byoung Koo Kim, Chang Heui Jang, In Sup Kim, Byong Sup Kim, Seong Cheol Byeon
LINK
71

2010
Corrosive Wear Test of Alloy 690 in Water Chemistry Environment at Room Temperature

Korean Nuclear Society

Seung Mo Hong, Changheui Jang, Sang Gyu Lee, In Sup Kim
LINK
70

2010
Evaluation of the corrosion resistance of the galvanized SS400 steel in NaCl solutions

U.S. Department of Energy Office of Scientific and Technical Information

Seung Mo Hong, Changheui Jang, In Sup Kim, Kyung Ho Lee, Byung Il Choi
LINK
69

2010
Tensile property evaluation of dissimilar metal welds containing alloy 82/182 fusion weld using miniature specimen

Proc. of KNS Spring Meeting, Chunchon, Korea. Small Sub-size Sp

Changheui Jang, Joung Hoon Lee, Sung Yup Jung, Jong Sung Kim, Tae Eun Jin
LINK
68

2010
Spatial variation of mechanical properties in alloy 82/182 dissimilar metal welds

6th ASINCO

Changheui Jang
LINK
67

2010
Fracture Toughness and Crack Growth Resistance of the Fine Grain Isotropic Graphite

Carbon letters

Daejong Kim, Seung Jin Oh, Changheui Jang, In Sup Kim, Se-Hwan Chi
LINK
66

2010
Approximation method for the calculation of stress intensity factors for the semi-elliptical surface flaws on thin-walled cylinder

Journal of mechanical science and technology

Changheui Jang
LINK
65

2010
Effects of hydrogen on the fatigue crack growth rate of low alloy steels

PROCEEDINGS OF THE 2006 INTERNATIONAL CONGRESS ON ADVANCES IN NUCLEAR POWER PLANTS

Sang Gyu Lee, Changheui Jang, IS Kim
LINK
64

2010
Reduction in fatigue life of SA508 Gr. 1a low alloy steel in 310C low oxygen-containing water

한국압력기기공학회 학술대회

Hyunchul Cho, Byoung Koo Kim, Changheui Jang, In Sup Kim, Hun Jang
LINK
63

2010
Cyclic Hardening Behaviors and Reduction in Fatigue Life of Type 316LN Austenitic Stainless Steel in 310° C Low Oxygen-Containing Water

International Conference on Nuclear Engineering

Hyunchul Cho, Byoung Koo Kim, Changheui Jang, In Sup Kim, Seung Mo Hong
LINK
62

2010
Irradiation embrittlement of cladding and HAZ of RPV steel

Nuclear Engineering and Technology

CH JANG, In Sup Kim, A KIMURA, JS LEE
LINK
61

2010
475℃ Embrittlement in High Chromium Oxide Dispersion Strengthened Steels

한국원자력학회 2005 년도 추계학술발표회

JS Lee, In Sup Kim, CH Jang, A Kimura, BG Kim, KN Choo, YS Choo, YH Kang
LINK
60

2010
Probabilistic Structural Integrity of Reactor Pressure Vessel under Pressurized Thermal Shock

Changheui Jang
LINK
59

2010
Probabilistic structural integrity of reactor vessel under pressurized thermal shock

IASMiRT

Myung Jo Jhung, Young Hwan Choi, Hho Jung Kim, Changheui Jang
LINK
58

2010
475. deg. C embrittlement in high chromium oxide dispersion strengthened steels

U.S. Department of Energy Office of Scientific and Technical Information

JS Lee, IS Kim, CH Jang, A Kimura, BG Kim, KN Choo, YS Choo, YH Kang
LINK
57

2010
X-ray diffraction measurements of ion-irradiated graphite

Proceedings of the Korean Nuclear Society Conference

Dae Jong Kim, Chang Heui Jang, In Sup Kim, Eung Seon Kim, Se Hwan Chi
LINK
56

2010
Cyclic Deformation Behavior of SA508 Gr. 1a Low Alloy Steel under Low Cycle Fatigue Loading in 310 ℃ Low Oxygen-Contained Water

한국원자력학회 2005 년도 춘계학술발표회

Hyunchul Cho, Byoung Koo Kim, Changheui Jang, In Sup Kim, Dae Yul Jung, Seong-Cheol Byeon
LINK
55

2010
Round robin analysis for probabilistic structural integrity of reactor pressure vessel under pressurized thermal shock

Journal of mechanical science and technology

Myung Jo Jhung, Changheui Jang, Seok Hun Kim, Young Hwan Choi, Hho Jung Kim, Sunggyu Jung, Jong Min Kim, Gap Heon Sohn, Tae Eun Jin, Taek Sang Choi, Ji Ho Kim, Jong Wook Kim, Keun Bae Park
LINK
54

2010
Low Cycle Fatigue Behaviors of Type 316 Stainless Steel in 310℃ Water Environment

Proceedings of the Korean Nuclear Society Conference

Byoung-Koo Kim, Hyun-Chul Cho, In-Sup Kim, Chang-Heui Jang, Dae-Yul Jung, Seong-Cheol Byeon
LINK
53

2010
Thermal aging embrittlement of high chromium oxide dispersion strengthened steels

Proceedings of the Korean Nuclear Society Conference

JS Lee, In Sup Kim, CH Jang, A Kimura, BG Kim, KN Choo, YS Choo, YH Kang
LINK
52

2010
Cyclic Deformation Behavior of SA508 Gr.1a Low Alloy Steel under Low Cycle Fatigue Loading in 310℃ Low Oxygen-Contained Water

Proceedings of the Korean Nuclear Society Conference

Hyun-Chul Cho, Byoung-Koo Kim, Chang-Heui Jang, In-Sup Kim, Dae-Yul Jung, Seong-Cheol Byeon
LINK
51

2010
Development of Experimental Method to Simulate the Corrosion Products in the Primary System of Nuclear Power Plant

Proceedings of the Korean Nuclear Society Conference

Sang-Hyun Kim, In-Sup Kim, Chang-Heui Jang
LINK
50

2010
Cyclic Stress Response and Fatigue Life of Type 316LN Stainless Steel in 310℃ Low Oxygen-containing Water

Proceedings of the Korean Nuclear Society Conference

Hyun-Chul Cho, Byoung-Koo Kim, Chang-Heui Jang, In-Sup Kim, Byong-Sup Kim, Seong-Cheol Byeon
LINK
49

2010
Mechanical Property Changes during Accelerated Thermal Aging Embrittlement Heat Treatment of Cast Stainless Steel, CF-8A

Proceedings of the Korean Nuclear Society Conference

Korean Nuclear Society
LINK
48

2010
Maintenance Technology Status of Korean Nuclear Power Plants; A Questionnaire Survey

Proceedings of the Korean Nuclear Society Conference

Jun-Seok Lee, Poong-Hyun Seong, Chang-Heui Jang, Hyuk-Soon Lim, Jang-Hwan Na, Seong-Jong Oh
LINK
47

2010
Comparative Study on the Technical Standards for the In-Service Inspection of Nuclear Power Plant Components in Several Countries

Korean Society for Nondestructive Testing

Ho-Sang Shin, Kyung-Jo Kim, Chang-Heui Jang, Suk-Chull Kang
LINK
46

2010
The effect of analysis variables on the failure probability of the reactor pressure vessel by pressurized thermal shock

Transactions of the Korean Society of Mechanical Engineers

Chang-Heui Jang, Myung-Jo Jhung, Suk-Chull Kang, Young-Hwan Choi
LINK
45

2010
The effects of the stainless steel cladding in pressurized thermal shock evaluation

Nuclear engineering and design

Changheui Jang, Suk-Chull Kang, Ho-Rim Moonn, Ill-Seok Jeong, Tae-Ryong Kim
LINK
44

2010
Corrosion fatigue cracking of low alloy steel in high temperature water

Corrosion Science and Technology

SG Lee, IS Kim, CH Jang, IS Jeong
LINK
43

2010
Comparision and prediction of mechnical properties for the thermally aged cast stainless steels

IAEA | 50 years of INIS

SY Cho, CH Jang, IS Jung
LINK
42

2010
PT limit curve construction for the reactor pressure vessel: heatup curve

IAEA | 50 years of INIS

CH Jang, HR Mun, IS Jeong, TR Kim
LINK
41

2010
Strain-life curve of SA508Cl. 3 pressure vessel steel in high temperature water environment

IAEA | 50 years of INIS

HC Cho, SK Lee, IC Kim, CH Jang, IS Jeong
LINK
40

2010
Experience of the integrity assessment of the highly embrittled reactor pressure vessel for the life extension

Nuclear engineering and design

SY Hong, C Jang, IS Jeong
LINK
39

2010
Construction of the PT limit curve for the nuclear reactor pressure vessel using influence coefficient methods: cooldown curve

Transactions of the Korean Society of Mechanical Engineers

CH Jang
LINK
38

2010
An Economic Assessment Methodology for Replacement of the Components of Nuclear Power Plant

ASME Pressure Vessels and Piping Conference

Ho-Rim Moonn, Changheui Jang, Jun-Hyun Park, Ill-Seok Jeong, Tae-Ryong Kim
LINK
37

2010
Stress intensity factor calculation for the axial semi-elliptical surface flaws on the thin-wall cylinder using influence coefficients

Transactions of the Korean Society of Mechanical Engineers A

Chang-Heui Jang, Ho-Rim Moon, Ill-Seok Jeong, Tae-Ryong Kim
LINK
36

2010
Initial RTNDT Re-evaluation of WF-233 weld for Kori unit 1 using master curve technology

IAEA | 50 years of INIS

Chang Heui Jang, Ill Seok Jeong, Tae Ryong Kim, Bong Sang Lee, Jun Hwa Hong
LINK
35

2010
The effect of hydrogen behavior on environmentally assisted cracking of vessel steel SA508C1. 3 in high temperature water environment

IAEA | 50 years of INIS

JW Kim, CH Jang, IS Jung, SG Lee, IS Kim
LINK
34

2010
Assessment of PWR reactor vessel internals and aging management program for lifetime management

IAEA | 50 years of INIS

SK Jeong, TE Jin, CH Jang, IS Jeong
LINK
33

2010
Development of the improved probabilistic fracture mechanics analysis code: VINTIN

IAEA | 50 years of INIS

CH Jang, HL Mun, IS Jeong, SY Hong
LINK
32

2010
Initial RT(NDT) Re-evaluation of WF-233 Weld of Kori Unit 1 using Master Curve Technology

Proceedings of the Korean Nuclear Society Conference

Jang Changheui, Ill-Seok Jeong, Tae-Ryong Kim, Bong-Sang Lee, Jun-Hwa Hong
LINK
31

2010
Fatigue management considering LWR coolant environments

Proceedings of the Korean Nuclear Society Conference

Heung-Bae Park, Tae-Eun Jin, Jang Changheui, Ill-Seok Jeong
LINK
30

2010
Comparison of Stress Intensity Factors for Longitudinal Semi-elliptical Surface Cracks in Cyclindrical Pressure Vessels

Proceedings of the KSME Conference

HR Moonn, CH Jang
LINK
29

2010
Stress Intensity Factor Calculation For The Semi-Elliptical Surface Flaws On The Thin-Wall Cylinder Using Influence Coefficients

Proceedings of the KSME Conference

Chang-Heui Jang, Ho-Rim Moonn, Ill-Seok Jeong
LINK
28

2010
Treatment of stainless steel cladding in pressurized thermal shock evaluation: deterministic analyses

Nuclear Engineering and Technology

Jang Changheui, Sung-Yull Hong
LINK
27

2010
Integrity assessment of the Kori Unit 1 reactor pressure vessel

Proc. of Korean Nuclear Society Autumn meeting

Ill-Seok Jeong, Changheui Jang, Sung-Yull Hong
LINK
26

2010
Methodology to decide optimum replacement term for components of nuclear power plants using decision analysis

IAEA | 50 years of INIS

HL Moon, CH Jang, JH Park, IS Jung
LINK
25

2010
Activities to Attain Integrity of Embrittled Reactor Pressure Vessel for Plant Lifetime Management Program

PVP 2000

Changheui Jang
LINK
24

2010
The Effect of Reference Flaw Size on PT Limit Curves for Pressurized Water Reactor

PVP 2000

Changheui Jang
LINK
23

2010
Probabilistic risk assessment of the pt limit curves for pressurized water reactors: cooldown curves

Changheui Jang, Ill-Seok Jeong, Sung-Yull Hong
LINK
22

2010
Fracture toughness master curve characterization of the low toughness linde 80 weld by small ABI and PCVN specimens

IAEA | 50 years of INIS

BS Lee, WJ Yang, JH Hong, CH Jang, SY Hong
LINK
21

2010
Plant-specific pressurized thermal shock integrity evaluation for Kori unit 1 reactor pressure vessel

Ill-Seok Jeong, Changheui Jang, Jun-Hyun Park, Sung-Yull Hong, Tae-Eun Jin, Sung-Gyu Jung, Hag-Gi Yuem
LINK
20

2010
A study on a probabilistic economic analysis method of steam generation replacement for nuclear power plants

U.S. Department of Energy Office of Scientific and Technical Information

HL Moon, CH Jang, JH Park, IS Jung
LINK
19

2010
The effect of flaw orientation on the integrity of PWR pressure vessel at the events of pressurized thermal shock

Nuclear engineering and design

Changheui Jang, Ill-Seok Jeong, Sung-Yull Hong
LINK
18

2010
A Probabilistic Fracture Mechanics Analysis for PTS Evaluation of Kori Unit 1 RPV

ASME

SG Jung, HS Kim, TE Jin, CH Jang, IS Jeong
LINK
17

2010
A study on the integrity evaluation for PWR vessel by PTS

IAEA | 50 years of INIS

SK Jung, TE Jin, CH Jang, IS Jung
LINK
16

2010
Pressurized thermal shock analyses of a reactor pressure vessel using critical crack depth diagrams

International journal of pressure vessels and piping

MJ Jhung, YW Park, C Jang
LINK
15

2010
The Estimation of Critical RTNDT and Probability of Failure for PWR vessels

IASMiRT

Sung-Gyu Jung, Hyun-Su Kim, Tae-Eun Jin, Chang-Heui Jang, Il-Seok Jeong
LINK
14

2010
Major components life evaluation for nuclear PLIM feasibility study

IASMiRT

IS Jeong, CH Jang
LINK
13

2010
Comparative study of probabilistic fracture mechanics codes

IAEA | 50 years of INIS

CH Jang, IS Jung, SK Jung, TE Jin
LINK
12

2010
Fatigue life evaluation of major components for nuclear power plant lifetime management

Changheui Jang, IS Jeong, SY Hong, TE Jin, SG Jung
LINK
11

2010
Korean nuclear power plant lifetime improvement study and future plan

IAEA | 50 years of INIS

IS Jeong, CH Jang, SY Hong
LINK
10

2010
Plant specific PTS analysis of Kori Unit 1

IAEA | International Nuclear Information System

Sung-Yull Hong, Changheui Jang, Ill-Seok Jeong, Tae-Eun Jin
LINK
9

2010
Nuclear Power Plant Lifetime Management Study (I)

U.S. Department of Energy Office of Scientific and Technical Information

Sung Yull Hong, Ill Seok Jeong, Chang Heui Jang, Taek Ho Song, Woo Young Song, Tae Eun Jin, Woo Chul Kim
LINK
8

2010
Fatigue tests and life estimation of Incoloy alloy 908

Advances in Cryogenic Engineering Materials

J Feng, LS Toma, CH Jang, MM Steeves
LINK
7

2010
Characterization of simulated production welds in alloy 908

Advances in Cryogenic Engineering Materials

CH Jang, DC Grundy, RG Ballinger, MM Steeves
LINK
6

2010
Weld development for Incoloy alloy 908, a low thermal expansion superalloy

Chang Heui Jang
LINK
5

2010
Development of a high toughness weld for Incoloy alloy 908

Advances in Cryogenic Engineering Materials

CH Jang, IS Hwang, RG Ballinger, MM Steeves
LINK
4

2010
US conductor R&D and small scale experiments for the ITER magnets

15th IEEE/NPSS Symposium. Fusion Engineering

JV Minervini, MM Steeves, DB Montgomery, R Randall, MK Takayasu
LINK
3

2010
A533B—1 Nuclear Pressure Vessel Steels

Journal of the Korean Nuclear Society

CH Jang
LINK
2

2010
A533B-1 원자로 압력용기 강의 미시적 파괴특성에 관한 연구

Journal of the Korean Nuclear Society

CH Jang, IS Kim
LINK
1

2010
A study on the microscopic fracture characteristics of A533B-1 nuclear pressure vessel steels

Nuclear Engineering and Technology

CH Jang, IS Kim, SP Park
LINK

PUBLICATION

Paper