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

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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