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

Showing results 6721 to 6740 of 10270

6721
Overview of the Radionuclide Inventory Assessment in Radioactive Waste Drums using the Scaling Factor Method in Korea

Lee, Kun Jai, EPRI Int'l LLW Conference (2005), 2005

6722
Overview of transport investigation related with X-ray imaging diagnostics on KSTAR

이승헌; 장시원; 홍주환; 장주혁; 전태민; 이상곤; 선창래; et al, 2013 KSTAR Conferene (2nd), NFRI, 2013-02

6723
Overview of transport study based on X-ray imaging and VUV diagnostics on KSTAR

Lee, Seungheon; Hong, Juhwan; Jang, Siwon; Jang, Juhyeok; Jun, Taemin; Kim, Jeonghui; Sun, Changrae; et al, 2013 A3 Foresight Program Workshop on Critical Physics issues Specific to Steady State Sustainment of High-Performance Plasmas, NFRI, NIFS, ASIPP, 2013-05

6724
Oxidation and mechanical behaviors of solid-solution hardening nickel-base superalloys in high temperature helium environments = 고용강화형 니켈기초합금의 고온헬륨환경에서의 산화 및 기계적 특성link

Kim, Dae-Jong; 김대종; et al, 한국과학기술원, 2010

6725
Oxidation and Volatilization of SiC Layer in High Temperature Steam

No, Hee-Cheon; Park,Byung Ha, ANS2014, ANS2014,, 2014-06-19

6726
Oxidation behavior and creep properties of alloy 617 at 900oC in Helium environments with various oxygen concentrations = 다양한 산소 농도에 따른 Alloy 617의 900℃ 헬륨환경에서의 크립 및 산화거동link

Koo, Ja-Hyun; 구자현; et al, 한국과학기술원, 2012

6727
Oxidation behavior of alumina-forming duplex stainless steels in high temperature steam environments = 고온 수증기 환경에서 알루미나 형성 듀플렉스 스테인리스강의 산화 거동link

Kim, Chaewon; Jang, Changheui; et al, 한국과학기술원, 2019

6728
Oxidation behavior of Fe-20Cr-25Ni-Nb austenitic stainless steel in high-temperature environment with small amount of water vapor

Chen, Hongsheng; Wang, Haibo; Sun, Qingzhu; Long, Chongsheng; Wei, Tianguo; Kim, Sung Hwan; Chen, Junjie; et al, CORROSION SCIENCE, v.145, pp.90 - 99, 2018-12

6729
Oxidation behavior of high-strength FeCrAl alloys in a high-temperature supercritical carbon dioxide environment

Chen, Hongsheng; Kim, Sung Hwan; Long, Chongsheng; Kim, Chaewon; Jang, Changheui, PROGRESS IN NATURAL SCIENCE-MATERIALS INTERNATIONAL, v.28, no.6, pp.731 - 739, 2018-12

6730
Oxidation Behaviors of Nickel-Base Superalloys in High Temperature Steam Environments

김동훈; 장창희; 구자현; 김대종; 유영성, Transactions of the Korean Society of Pressure Vessels and Piping, v.7, pp.26 - 33, 2011-02

6731
Oxidation behaviors of wrought Nickel-base superalloys in high temperature nuclear environments

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

6732
Oxidation behaviors of wrought nickel-based superalloys in various high temperature environments

Jang, Chang-Heui; Kim, Dae-Jong; Kim, Dong-Hoon; Sah, In-Jin; Ryu, Woo-Seog; Yoo, Young-sung, TRANSACTIONS OF NONFERROUS METALS SOCIETY OF CHINA, v.21, no.7, pp.1524 - 1531, 2011-07

6733
Oxidation behaviour of an Alloy 617 in very high-temperature air and helium environments

Jang, Changheui; Lee, Daejin; Kim, Daejong, INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, v.85, no.6, pp.368 - 377, 2008-06

6734
Oxidation Characteristics and Oxide Layer Evolution of Alloy 617 and Haynes 230 at 900 A degrees C and 1100 A degrees C

Kim, Daejong; Jang, Changheui; Ryu, Woo Seog, OXIDATION OF METALS, v.71, no.5-6, pp.271 - 293, 2009-06

6735
Oxidation characteristics of Nickel-base superalloys at high temperature in air and helium atmospheres

Lee, D.; Kim, D.; Jang, Changheui, 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

6736
Oxidation characteristics of the electron beam surface-treated Alloy 617 in high temperature helium environments

Lee, Ho Jung; Sah, Injin; Kim, Dong-Hoon; Kim, Hyunmyung; Jang, Chang-Heui, JOURNAL OF NUCLEAR MATERIALS, v.456, pp.220 - 227, 2015-01

6737
Oxidation effects on the fracture toughness of the nuclear graphite at high temperature = 고온에서 원자력급 흑연의 파괴인성에 대한 산화 효과 연구link

Kim, Byung-jun; 김병준; et al, 한국과학기술원, 2008

6738
Oxidation Effects on the Strength and Fracture Toughness of the Selected Nuclear Graphite Grades at 600 ¡ÆC

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

6739
Oxidation mechanism and kinetics of nuclear-grade FeCrAl alloys in the temperature range of 500-1500 degrees C in steam

Kim, Chaewon; Tang, Chongchong; Grosse, Mirco; Maeng, Yunhwan; Jang, Changheui; Steinbrueck, Martin, JOURNAL OF NUCLEAR MATERIALS, v.564, 2022-06

6740
Oxidation of Inconel alloy 617 at the Elevated Temperature Air Environment

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

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