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

Showing results 79 to 98 of 98

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

경도시험을 이용한 주철의 선택적침출 평가

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

고온가스로용 니켈기초합금의 확산접합 기술 개발

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

원자력급 흑연의 파괴인성 평가

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

인코넬 82/182 이종금속 용접부의 기계물성 평가

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

초고온가스로의 중간열교환기 재료의 고온특성평가

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

환경피로의 실험적연구

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



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