Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" byAuthor1266

Showing results 29 to 88 of 98

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

61
Low Cycle Fatigue Behaviors of Low Alloy Steels and Stainless Steels in Deoxygenated High Temperature Water

Jang, Changheuiresearcher, the 12th International Conference on Pressure Vessel Technology, 2009-09-21

62
Maintenance Technology Status of Korean Nuclear Power Plants: A Questionnaire Survey

Seong, Poong-Hyunresearcher; Jang, Changheuiresearcher; Lee, Jun Seok; Lim, Hyuk Soon; Na, Jang Hwan; Oh, Seong Jong, 한국원자력학회 2005 추계학술대회, 한국원자력학회, 2005-10

63
Major components life evaluation for nuclear PLIM feasibility study

Jang, Changheuiresearcher, 15th International Conference on Structural Mechanics in Reactor Technology, 1999-08-16

64
Mechanical Properties Evaluation in Inconel 82/182 Dissimilar Metal Welds

Jang, Changheuiresearcher, 19th International Conference on Structural Mechanics in Reactor Technology (SMiRT 19), 2007-08-13

65
Mechanical Property Changes During Accelerated Thermal Aging Embrittlement Heat Treatment of Cast Stainless Steel, CF-8A

Wann, KhingMay; Lee, Joo Suk; Jang, Changheuiresearcher, 한국원자력학회 2005년도 추계학술발표회 , pp.993 - 994, 한국원자력학회, 2005-10

66
Metal corrosion resistances in high temperature hydriodic aicd gas environment for SI cycle

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

67
Oxidation behaviors of wrought Nickel-base superalloys in high temperature nuclear environments

Jang, Changheuiresearcher, IUMRS 11th International Conference in Asia, 2010-09-28

68
Oxidation characteristics of Nickel-base superalloys at high temperature in air and helium atmospheres

Lee, D.; Kim, D.; Jang, Changheuiresearcher, Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, The Nuclear Renaissance at Work, pp.2360 - 2365, 2007-05-13

69
Oxidation Effects on the Strength and Fracture Toughness of the Selected Nuclear Graphite Grades at 600 ¡ÆC

Kim, Byung Jun; Kim, Daejong; Jang, Changheuiresearcher; Chi, Se-Hwan, CARBON 2007, 2007-07-18

70
Oxidation of Inconel alloy 617 at the Elevated Temperature Air Environment

Lee, Daejin; Lee, Sanggyu; Jang, Changheuiresearcher, Korea Nuclear Society, Korea Nuclear Society, 2006

71
Plant Specific PTS Analysis of Kori Unit 1

Jang, Changheuiresearcher, IAEA Specialist Meeting 1997, 1997-05-06

72
Prediction of PT diametral creep for candu reactors using fuzzy neural networks

Lee, J.Y.; Na, M.G.; Yang, H.Y.; Lee, S.H.; Jang, Changheuiresearcher; Kim, D., 6th American Nuclear Society International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies 2009, v.2, pp.1133 - 1143, 2009-04-05

73
Pressurized Thermal Shock Evaluation of the Kori Unit 1 Nuclear Power Plant

Jang, Changheuiresearcher, PVP 2000, 2000-07-24

74
Probabilistic fracture mechanics application for Alloy 600 components in PWRS

Hong, J.-D.; Jang, Changheuiresearcher, International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010, pp.1973 - 1978, 2010-06-13

75
Probabilistic Fracture Mechanics Application For Alloy 82/182 Welds In PWRs

Hong, Jong-Dae; Jang, Changheuiresearcher, Pressure Vessels & Piping (PVP) 2010, 2010-07-20

76
Probabilistic Fracture Mechanics Application for PWSCC Risk Evaluation of Ni-base alloy welds in PWR

Jang, Changheuiresearcher; Jong-Dae Kim, ICG-EAC 2012, IGCEAC, 2012-05-14

77
Probabilistic Structural Integrity of Reactor Pressure Vessel under Pressurized Thermal Shock

Jang, Changheuiresearcher, SMiRT-18, 2005-08-10

78
PWR 운전환경이 Alloy 690의 피로수명에 미치는 영향

장창희researcher; 홍종대, 2012 KPVP Annual meeting, 한국압력기기공학회, 2012-11-23

79
Reduction in fatigue life of SA508 Gr.1a low alloy steel in 310C low oxygen-containing water

Cho, Hyunchul; Kim, Byoung Koo; Jang, Changheuiresearcher; Kim, In Sup; Jang, Hun, 한국압력기기공학회 학술대회, 한국압력기기공학회, 2006

80
Reduction in fatigue life of type 316LN stainless steel in 310 C low oxygen-containing water

Cho, Hyun-Chul; Kim, Byoung-Koo; Jang, Changheuiresearcher; Kim, In Sup; Kim, Byong-Sup; Byeon, Seong-Cheol, 한국원자력학회 2005년도 추계학술발표회, 한국원자력학회, 2005-10-27

81
SA508 Gr.3 Cl2 저합금강 모재와 용접부의 290oC 순수 환경에서 피로균열거동 분석

장창희researcher; 김정현; 홍종대; 나경환; 이재곤, 2012 한국부식방식학회 춘계학술대회, 사단법인 한국부식방식학회, 2012-05-18

82
Spatial Variation of Mechanical Properties in Alloy 82/182 Dissimilar Metal Welds

Jang, Changheuiresearcher, 6th ASINCO, 2006-04-25

83
Study on Low Cycle Fatigue Behavior of Type 316 Stainless Steel in a 310C Water Environment

Jang, Changheuiresearcher, International Conference on Water Chemistry of Nuclear Reactor Systems, 2006-10-24

84
The effect of corrosion product on the corrosion resistance of the galvanized steel in NaCl solutions

Jang, Changheuiresearcher; Hong, S. M.; Lee, S. J.; Kim, J. M.; Lee, S. H., ISRSM2007, 2007

85
The effect of material variability on low cycle fatigue resistance of low alloy steels in a 310oC deoxygenated water

Jang, H.; Hong, J.-D.; Lee, J.G.; Jang, Changheuiresearcher, 714th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009, v.2, pp.945 - 951, 2009-08-23

86
The Effect of Reference Flaw Size on P-T Limit Curves for Pressurized Water Reactor

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

87
The Effect of the material variability on the fatigue life of low alloy steels in 310oC deoxygenated water

Jang, Changheuiresearcher, 2008 ICG-EAC Meeting, 2008-04-22

88
The Effects of Dissolved Hydrogen Contents on the Low Cycle Fatigue Behaviors of a 316LN Stainless Steel in Simulated PWR Condition

Jang, Changheuiresearcher; Cho, Pyung-Yeon; Hong, Jong-Dae; Jang, Hun; Kim, Tae-Soon; Lee, Jae-Gon, Nuclear Plant Chemistry Conference 2010, 2010-10-05

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