Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author 1266

Showing results 1 to 60 of 98

1
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

2
Activities to Attain Integrity of Embrittled Reactor Pressure Vessel for Plant Lifetime Management Program

Jang, Changheuiresearcher, PVP 2000, 2000-07-25

3
An Economic Assessment Methodology for Replacement of the Components of Nuclear Power Plant

Jang, Changheuiresearcher, Proc. of PVP2002, 2002-09-30

4
Analysis on Plant-Specific PTS Integrity for a Pressurized Water Reactor Vessel

Jang, Changheuiresearcher, 9th ICPVT, 2000-04-10

5
Application of Fracture Mechanics for the Integrity Analysis of Reactor Pressure Vessel

Jang, Changheuiresearcher, 16th Pacific Basin Nuclear Conference (16PBNC), 2008-10-16

6
Application of Probabilistic Fracture Mechanics for Reactor Pressure Vessel Integrity Evaluation

Jang, Changheuiresearcher, The Japan-Korea Joint Seminar on Nuclear Reactor Fuel and Materials, 2005-03-05

7
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

8
Characterization of Oxidation and Oxide Layers of Nickel-Base Superalloys at High Temperature

Jang, Changheuiresearcher, OECD NEA NSC Workshop on Structural Materials for Innovative Nuclear Systems (SMINS), 2007-06-05

9
Characterization of Simulated Production Welds in Alloy 908

Jang, Changheuiresearcher, Advances on Cryogenic Engineering, 1996-07-15

10
Comparative study of fatigue life of type 316LN austenitic stainless steel in 310C low oxygen-containing water with prediction models

Kim, Byoung Koo; Jang, Changheuiresearcher; Kim, In Sup; Kim, Byong Sup; Byeon, Seong Cheol, Korea Nuclear Society, Korea Nuclear Society, 2006

11
Corrosion resistance of materials at high temperature under gas phase of sulfuric acid for IS cycle

Jang, Changheuiresearcher; Young Soo Kim; Jin Young Choi; In Jin Sah; No, Hee Cheonresearcher, 2012 American Nuclear Society Winter Meetings, American Nuclear Society, 2011-11-14

12
Corrosion Resistance of Surface treated Alloy 617 in High Temperature HI and H2SO4 Environments

Jang, Changheuiresearcher; Injin Sah; Jin Young Choi; Young Soo Kim; No, Hee Cheonresearcher; Jin Young Choi, 2012 Materials Research Society, Materials Research Society, 2012-11-28

13
Corrosive Wear of Alloy 690 Tubes in Alkaline Water

Jang, Changheuiresearcher, International Corrosion Engineering Conference, 2007-05-22

14
Corrosive Wear Test of Alloy 690 in Water Chemistry Environment at Room-temperature

Hong, Seung Mo; Jang, Changheuiresearcher; Lee, Sang Gyu; Kim, In Sup, Korean Nuclear Society, Korean Nuclear Society, 2006

15
Creep behaviors of alloy 617 at temperatures between 800 and 1000WOC

Kim, D.; Jang, Changheuiresearcher; Ryu, W.S., International Conference on Advances in Nuclear Power Plants, ICAPP 2008, pp.2158 - 2162, 2008-06-08

16
Creep Behaviors of Alloy 617 in High Temperature Steam Environments

Jang, Changheuiresearcher; Donghoon Kim; Injin Sah; Jahyun Koo, NFSM 2012, American Nuclear Society, 2012-06-26

17
Creep Behaviors of Nickel-Base Superalloys Alloy 617 and Haynes 230 at High Temperature

Jang, Changheuiresearcher, 2009 International Congress on Advances in Nuclear Power Plants, 2009-05-12

18
Creep resistance of Alloy 617 in high temperature helium environments

Jang, Changheuiresearcher; Ho Jung Lee; Injin Sah; Jahyun Koo; Dae Jong Kim, Asia Pacific Conference on Fracture Strength-Machanical and materials 2012, Korean Society of Mechanical Engineering(KSME), 2012-05-14

19
Creep-environment interactions of Alloy 617 at elevated temperature

Kim, D.; Jang, Changheuiresearcher; Ryu, W.S., ASME 2008 Pressure Vessels and Piping Conference, PVP2008, pp.1215 - 1220, 2008-07-27

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 hardening behaviors and reduction in fatigue life of type 316LN austenitic stainless steel in 310째C low oxygen-containing water

Cho, H.; Kim, B.K.; Jang, Changheuiresearcher; Kim, I.S.; Hong, S.M., Fourteenth International Conference on Nuclear Engineering 2006, ICONE 14, 2006-07-17

23
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

24
Determination of the Initial RTNDT using Master Curve Technology and Implication to RPV Integrity Assessment for Life Extension

Jang, Changheuiresearcher, IAEA specialists Meeting on Master Curve Technology, 2001-09-18

25
Development of a probabilistic fracture mechanics code for primary system pipes and application for RI-ISI

Jang, Changheuiresearcher; Datta, D.; Yang, J.-S., ASME 2008 Pressure Vessels and Piping Conference, PVP2008, pp.439 - 446, 2008-07-27

26
Development of High Toughness Weld for Incoloy Alloy 908

Jang, Changheuiresearcher, Advances on Cryogenic Engineering, 1994-07-15

27
Diametral creep prediction of pressure tube using statistical regression methods

Kim, D.; Lee, J.Y.; Na, M.G.; Jang, Changheuiresearcher, 31st Annual Conference of the Canadian Nuclear Society and 34th CNS/CNA Student Conference 2010, pp.514 - 520, 2010-05-24

28
Diffusion bonding of Ni-base superalloys for the application of VHTR intermediate heat exchanger

Jang, Changheuiresearcher; Injin Sah; Donghoon Kim, International Welding Joining Conference-Korea 2012, The Korean Welding and Joining Society, 2012-11-23

29
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

30
Effect of Niobium content on hydride embrittlement of zirconium alloys

Jang, Changheuiresearcher, 2008 Water Reactor Fuel Performance Meeting(WRFPM), 2008-10-20

31
Effects Al Contents in the Surface Micro-Alloying Region on the High Temperature Oxidation Behaviors of Alloy 617

Jang, Changheuiresearcher; Ho Jung Lee; Donghoon Kim; Injin Sah, NFSM 2012, American Nucealr Society, 2012-06-26

32
Effects of Carburization and Decarburization on Mechanical Properties of Nickel-Base Superalloys

Kim, D; Sah, I; Jang, Changheuiresearcher, Proceeding of the 12th International Conference on Pressure Vessel Technology, 2009-09-22

33
Effects Of Carburization and Decarburization On The Mechanical Properties Of Nickel-Base Superalloys For VHTR Applications

Kim, D; Sah, I; Jang, Changheuiresearcher, Structural Materials for Innovative Nuclear System(SMINS) -2, 2010-09-01

34
Effects of hydrogen on the fatigue crack growth rate of low alloy steels

Lee, S.G.; Jang, Changheuiresearcher; Kim, I.S., American Nuclear Society Embedded Topical Meeting - 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06, pp.2124 - 2128, 2006-06-04

35
Effects of Material Variability and Dissolved Hydrogen Content on LCF of 316LN

Jang, Changheuiresearcher, ICG-EAC 2010, 2010-04-13

36
Environmental Fatigue Behaviors of SA508 Gr.1a Low Alloy Steel in 310oC Deoxygenated Water

Jang, Changheuiresearcher, Key Engineering Materials, v.345, pp.1039 - 1042, Trans Tech Publications Ltd., 2007-06

37
Environmental Fatigue Behaviors of Type 316LN Stainless Steels in Simulated PWR Water with Different Dissolved Hydrogen Contents

Jang, Changheuiresearcher, Proceeding of the 12th International Conference on Pressure Vessel Technology, 2009-09-22

38
Environmental Fatigue Behaviors of Wrought and Cast Stainless Steels in 310oC Deoxygenated Water

Cho, P; Jang, H; Jeong, I; Lee, J; Jang, Changheuiresearcher, 2009 International Congress on Advances in Nuclear Power Plants, ICAPP 2009, 2009-05-12

39
Environmental Fatigue Tests in the Deaerated High Temperature Water

Jang, Changheuiresearcher; Cho, Hyunchul; Jang, Hun; Kim, In Sup; Moon, Chan Kook, 2007 KEPIC Week, 2007

40
Estimation of Pressure Tube Diametral Creep for CANDU Reactors Using Fuzzy Neural Networks

Jang, Changheuiresearcher, 6th International Topical Meeting on Nuclear Plant Instrumentation Control and Human Machine Interface Technology, 2009-04-07

41
Evaluation Of Creep Resistance And Dynamic Recrystallization Of Alloy 617 At Elevated Temperatures

Jang, Changheuiresearcher, HTMTC Workshop on Mechanical Testing for Next Generation Nuclear Systems: Requirements, Testing Methodologies and Data Applications, 2008-04-17

42
Evaluation of Fracture Toughness, Chemistry and Microstructural Factors of the Linde 80 WF-233 Weldment

Jang, Changheuiresearcher, IAEA specialists Meeting on Methodology and Supporting Research for Pressurized Thermal Shock Evaluation, 2000-07-19

43
Evaluation of the Microstructure and Mechanical Properties of the Stainless Steel Narrow Gap Welds in Piping

Jang, Changheuiresearcher, World Conference on Safety of Oil and Gas Industry 2007 (WCOGI 2007), 2007-04-12

44
Failure assessment of nuclear piping components due to combined degradation mechanisms by an advanced probabilistic fracture mechanics code

Datta, D.; Jang, Changheuiresearcher, 2009 ASME Pressure Vessels and Piping Conference, PVP 2009, pp.687 - 694, 2009-07-26

45
Failure probability assessment of a PWR Primary System Piping subcomponents under different loading conditions

Jang, Changheuiresearcher; Datta, D., Second Int. Symp. on Nuclear Power Plant Life Management, 2007

46
Fatigue Crack Growth and Fracture Resistance of the Stainless Steel Narrow Gap Welds in Nuclear Piping System

Jang, Changheuiresearcher, 7th ASINCO, 2008-07-03

47
Fatigue Life Evaluation of Major Components for Nuclear Power Plant Lifetime Management

Jang, Changheuiresearcher, 14th International Conference on Structural Mechanics in Reactor Technology, 1997-08-20

48
Fatigue Test and Life Estimation of Incoloy 908

Jang, Changheuiresearcher, Advances on Cryogenic Engineering, 1996-07-15

49
Fracture Behaviors of Isotropic Nuclear Graphite

Jang, Changheuiresearcher, CARBON 2006, 2006-07-18

50
Fracture toughness of IG-11 graphite with crack size measurement methods

Kim, D.; Jang, Changheuiresearcher; Chi, S.-H., 2006 Winter Meeting of the American Nuclear Society, pp.101 - 102, 2006-11-12

51
High Temperature Oxidation Characteristics of Surface Treated Alloy 617 by Al Sputtering and Inter-Diffusion Heat Treatment

Kim, Donghoon; Koo, Jahyun; Jang, Changheuiresearcher, International Congress on Advances in Nuclear Power Plants (ICAPP 2011), 2011-05-03

52
Hot Steam Corrosion Behavior of Ni-based Superalloys at High Temperature Steam Environments

Kim, Donghoon; Kim, Minu; Lee, Hyun Min; Kim, Daejong; Jang, Changheuiresearcher; Yoon, Duk-Joo, TMS 2010 Spring Meeting, 2010-02-15

53
Hot steam corrosion characteristics of Ni-base superalloys for intermediate heat exchangers of HTSE system

KIM, Donghoon; KIM, Daejong; KOO, Jahyun; DUK, JOO YOON; Jang, Changheuiresearcher, 2010 ANS Annual Meeting and Embedded Topical Meetings, pp.863 - 864, 2010-06-13

54
Incorporation of materials’ sensitive simulation technique into the PINTIN-CAM code for integrity of nuclear piping system

Jang, Changheuiresearcher, Pressure Vessels & Piping 2010, 2010-07-20

55
Integrity of Ni-base superalloys for advanced nuclear systems application - environment and materials interaction

Jang, Changheuiresearcher; Kim, D; Kim, D; Kim, M; Sah, I; Ryu, WS; Yoon, DJ, Structural Materials for Innovative Nuclear System (SMINS)-2, 2010-09-01

56
Irradiation Embrittlement of Cladding and HAZ of RPV Steel

Jang, Changheuiresearcher; Kim, In Sup; Lee, J.S.; Kimura, A., International Symposium on Research Reactor and Neutron Science, 2005-04-15

57
Korean Nuclear Power Plant Lifetime Improvement Study and Future Plan

Jang, Changheuiresearcher, 12th KAIF/KNS Annual Conference, 1997-04-03

58
Korean PMMD: Approach and prospect

Hwang, I.S.; Kang, S.C.; Hong, J.H.; Jang, Changheuiresearcher, ANS 2009 Spring Meeting, v.100, pp.411 - 412, 2009-06-14

59
Leak Failure Analysis for Reactor Coolant Loop in a Nuclear Power Plant

Jang, Changheuiresearcher, 16th Pacific Basin Nuclear Conference (16PBNC), 2008-10-15

60
Life beyond 60 years: Korean perspectives

Jang, Changheuiresearcher; Hwang, II S., 714th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009, v.2, pp.1557 - 1570, 2009-08-23

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