Paper
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20
An Assessment of the Integrity of the PWR Vessels An Assessment of the Integrity of the PWR Vessels, 1982
Journal of nuclear science and technologyMyung Jo Jhung, Seok Hun Kim, Young Hwan Choi, Yoon Suk CHANG, Xiangyuan XU, Jong Min KIM, Jong Wook KIM, Changheui JANGLINK -
19
Stress Intensity Factors for Circumferential Surface Cracks in Pipes and Rods under Tension and Bending Loads
Journal of nuclear science and technologyMyung Jo Jhung, Seok Hun Kim, Young Hwan Choi, Yoon Suk CHANG, Xiangyuan XU, Jong Min KIM, Jong Wook KIM, Changheui JANGLINK -
18
Boiler and Pressure Vessel Code Boiler and Pressure Vessel Code Section XI, 2004
Journal of nuclear science and technologyMyung Jo Jhung, Seok Hun Kim, Young Hwan Choi, Yoon Suk CHANG, Xiangyuan XU, Jong Min KIM, Jong Wook KIM, Changheui JANGLINK -
17
VISA-II : A Computer Code for Predicting the Probability of Reactor Vessel Failure
Journal of nuclear science and technologyMyung Jo Jhung, Seok Hun Kim, Young Hwan Choi, Yoon Suk CHANG, Xiangyuan XU, Jong Min KIM, Jong Wook KIM, Changheui JANGLINK -
16
Documentation of Probabilistic Fracture Mechanics Codes Used for Reactor Pressure Vessels Subjected to Pressurized Thermal Shock Loading
Journal of nuclear science and technologyMyung Jo Jhung, Seok Hun Kim, Young Hwan Choi, Yoon Suk CHANG, Xiangyuan XU, Jong Min KIM, Jong Wook KIM, Changheui JANGLINK -
15
Probabilistic fracture mechanics round robin analysis of reactor pressure vessels during pressurized thermal shock
Journal of nuclear science and technologyMyung Jo Jhung, Seok Hun Kim, Young Hwan Choi, Yoon Suk Chang, Xiangyuan Xu, Jong Min Kim, Jong Wook Kim, Changheui JangLINK -
14
Effects of high temperature aging in an impure helium environment on low temperature embrittlement of Alloy 617 and Haynes 230
Journal of Nuclear MaterialsDaejong Kim, Injin Sah, Changheui JangLINK -
13
Effects Of Carburization and Decarburization On The Mechanical Properties Of Nickel-Base Superalloys For VHTR Applications
Structural Materials for Innovative Nuclear Systems (SMINS-2)Daejong Kim, Injin Sah, Changheui JangLINK -
12
Integrity of Ni-base superalloys for advanced nuclear systems application-environment and materials interaction
Structural Materials for Innovative Nuclear System (SMINS)-2Changheui Jang, D Kim, M Kim, I Sah, WS Ryu, DJ YoonLINK -
11
Hot Steam Corrosion Characteristics of Ni-Base Superalloys for Intermediate Heat Exchangers of HTSE System
TransactionsDonghoon Kim, Daejong Kim, Jahyun Koo, Duk Joo Yoon, Changheui JangLINK -
10
Diametral creep prediction of pressure tube using statistical regression methods
31st Annual Conference of the Canadian Nuclear Society and 34th CNS/CNA Student Conference 2010D Kim, JY Lee, MG Na, Changheui JangLINK -
9
Diametral Creep Prediction of the Pressure Tubes in CANDU Reactors Using a Genetic Optimized Linear Model
IAEA | 50 years of INISSung Han Lee, Young Gyu No, Man Gyun Na, Jae Yong Lee, Chang Heui Jang, Dong Hoon KimLINK -
8
Effects of microstructure and residual stress on fatigue crack growth of stainless steel narrow gap welds
Materials & DesignChangheui Jang, Pyung-Yeon Cho, Minu Kim, Seung-Jin Oh, Jun-Seog YangLINK -
7
Effect of Nb on hydride embrittlement of Zr–xNb alloys
Materials Science and Engineering: ASeungjin Oh, Changheui Jang, Jun Hwan Kim, Yong Hwan JeongLINK -
6
Hot Steam Corrosion Behavior of Ni-based Superalloys at High Temperature Steam Environments
TMS 2010 Spring MeetingDonghoon Kim, Minu Kim, Hyun Min Lee, Daejong Kim, Changheui Jang, Duk-Joo YoonLINK -
5
Probabilistic fracture mechanics application for Alloy 600 components in PWRs
IAEA | 50 years of INISJong-Dae Hong, Changheui JangLINK -
4
Effects of Crack Measurement Methods on The Determination of Fracture Toughness of IG-110 Isotropic Graphite
IAEA | 50 years of INISSe Hwan Chi, Dae Jong Kim, Chang Heui JangLINK -
3
Prediction of the Fundamental Mode Lamb Wave Reflection from a Crack-Like Discontinuity Using Eigen-Mode Expansion
Journal of the Korean Society for Nondestructive TestingJae-Seok Park, Chang-Heui Jang, Jong-Po LeeLINK -
2
Incorporation of Materials’ Sensitive Simulation Technique Into the PINTIN-CAM Code for Integrity of Nuclear Piping System
Pressure Vessels and Piping ConferenceDebashis Datta, Changheui JangLINK -
1
Probabilistic Fracture Mechanics Application for Alloy 82/182 Welds in PWRs
Pressure Vessels and Piping ConferenceJong-Dae Hong, Changheui JangLINK