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

Showing results 54 to 98 of 98

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

89
The estimation if critical RTNDT and probability of failure for PWR vessels

Jang, Changheuiresearcher, 15th International Conference on Structural Mechanics in Reactor Technology, 1999-08-17

90
The high temperature oxidation behaviors of several nickel base superalloys

Daejin, L.; Sanggyu, L.; Jang, Changheuiresearcher, 2006 Winter Meeting of the American Nuclear Society, pp.105 - 106, 2006-11-12

91
Thermal Aging Embrittlement of High Chromium Oxide Dispersion Strengthening Steels

Lee, J.S; Kim, In Sup; Jang, Changheuiresearcher; Kimura, A.; Kim, B.G.; Choo, KN; Choo, Y.S; et al, 한국원자력학회 2005년도 춘계학술발표회, pp.471 - 472, 한국원자력학회, 2005-05-26

92
Thermal Aging Embrittlement of High Cr Oxide Dispersion Strengthened Steels

Jang, Changheuiresearcher; Kim, In Sup; Lee, J.S.; Kimura, A., ICFRM-12, 2005-12-07

93
경도시험을 이용한 주철의 선택적침출 평가

장창희researcher; 김정현; 홍종대; 조평현; 조현철, 원전수화학 및 부식 WS, 원자력학회. 원자력연구원, 2012-06-21

94
고온가스로용 니켈기초합금의 확산접합 기술 개발

장창희researcher; 김동훈; 사인진, 2012 대한기계학회 춘계학술대회 재료 및 파괴부문 , 사단법인 대한기계학회, 2012-02-16

95
원자력급 흑연의 파괴인성 평가

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

96
인코넬 82/182 이종금속 용접부의 기계물성 평가

이정훈; 장창희researcher; 김종성; 진태은, 대한기계학회 2007년 춘계학술대회, pp.244 - 249, 대한기계학회, 2007-05-30

97
초고온가스로의 중간열교환기 재료의 고온특성평가

장창희researcher; 김동훈; 사인진; 이호중, 2012 금속재료학회 추계학술대회, 대한금속재료학회, 2012-10-25

98
환경피로의 실험적연구

장창희researcher; 홍종대; 장훈, 2012 KEPIC Week, 대한전기협회, 2012-08-30

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