Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Type Conference
Showing results 1821 to 1840 of 5616
| Development of the Simulation Code for the Tritium Behavior Analysis in the Pebble Type Gas Cooled Reactor for the Hydrogen Production Lee, Kun Jai, PBNC (Pacific Basin Nuclear Conference) 2006, 2006 |
| Development of the System Dynamics Code using Homogeneous Equilibrium Model for SCO2 Brayton cycle Transient Analyses Bae, Seong Jun; Lee, Won Woong; Oh, Bongseong; Lee, Jeong-Ik, The Korean Nuclear Society Autumn Meeting(2016), The Korean Nuclear Society, 2016-10-27 |
| Development of the Ultrasonic Method for Two-Phase Mixture Level Measurement No, Hee Cheon; Lee, DW, 2nd Japan-Korea Sym. on Nuclear thermal Hydraulics and Safety, 2000 |
| Development of the ultrasonic method for two-phase mixture level measurement No, Hee Cheon; Lee, Dong Won, 한국원자력학회 춘계발표회, 한국원자력학회, 1999 |
| Development of Thermal-Hydraulic Analysis Code for Annular Fuel-Based Assemblies Han, KH; Chang, Soon-Heung, The 3rd Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, 2002 |
| Development of Thermal-Hydraulic Safety Codes for HTGRS WITH GAS-TURBLNE AND HYDROGEN PROCESS CYCLES No, Hee Cheon, NTHAS6 2008 |
| Development of Throughflow Calculation Code for Axial Flow Compressors No, Hee Cheon; Kim, Ji-Hwan; Kim, Hyeun-Min, KNS Spring Meeting, pp.39 - 40, Korean Nuclear Society, 2005-05-26 |
| Development of Throughflow Calculation Code for Axial Flow Compressors No, Hee Cheon; Kim, Ji Hwan; Kim, Hyeun Min, 한국원자력학회 춘계발표회, 한국원자력학회, 2005 |
| Development of Tomographic Reconstruction method for ITER VUV diagnostics 장주혁; 이승헌; 홍주환; 장시원; 전태민; 선창래; 최원호, 2013 KSTAR Conferene (2nd), NFRI, 2013-02 |
| Development of Transient Fuel Performance Analysis System for Ultra Long-Life Micro Lead-Cooled Fast Reactor 문지원; 류호진, 한국원자력학회 2022 춘계학술발표회, 한국원자력학회, 2022-05-19 |
| Development of tritium and helium inventory code for tritium storage and delivery system Lee S.; Yook D.; Lee, Kun Jai; Song K.-M.; Shon S.H., 2008 Winter Meeting and Nuclear Technology Expo: Nuclear Power-Ready, Steady, Go, pp.247 - 248, 2008-11-09 |
| Development of Tritium Inventory Code for Tritium Handling System in Korea Lee, Kun Jai, 31st Tritium Focus Group Meeting, 2008 |
| Development of Tungsten Based High Entropy Alloys with Enhanced High Temperature Mechanical Properties (Invited) Waseem, Owais Ahmed; Ryu, Ho Jin; Hong, Soon Hyung; Lee, Junho; Kim, Seung Su, KSTAR conference, KSTAR, 2016-02-25 |
| Development of Tungsten Injection System for Impurity Accumulation Study in KSTAR Plasma Lee, H.Y; Hong, Suk-Ho; Hong, Joohwan; Lee, Seung Hun; Jang, Siwon; Jang, Juhyeok; Jeon, Taemin; et al, 30th The Japan Society of Plasma Science and Nuclear Fusion Research Annual meeting, The Japan Society of Plasma Science and Nuclear Fusion Research, 2013-12-04 |
| Development of Tungsten Injection System for Impurity Transport Study in KSTAR Lee, H.Y.; Hong,Suk-Ho; Hong, Joohwan; Lee, Seung Hun; Jang, Siwon; Jang, Juhyeok; Jeon, Taemin; et al, Asia Plasma and Fusion Association Conference, NFRI, 2013-11-06 |
| Development of Unavailability Estimation Method Considering Various Operating States of Dynamic Systems 신승기; 강현국; 성풍현, 한국원자력학회 2011 추계학술발표대회, 한국원자력학회, 2011-10-27 |
| Development of W based alloys for oxidation resistance via powder metallurgy 김승수; 류호진, 한국분말야금학회 2017 추계학술대회, 한국분말야금학회, 2017-11-02 |
| Development of Work Verification System for Cooperation between MCR Operators and Field Workers in Nuclear Power Plants Lee, Seung Min; Seong, Poong-Hyun, 한국원자력학회 2014 춘계발표대회, 한국원자력학회, 2014-05-29 |
| Development of WxTaTiVCr-based composites for fusion plasma facing applications by powder metallurgy Waseem, Owais Ahmed; 류호진, 한국분말야금학회 2018 추계학술대회, 한국분말야금학회, 2018-11-14 |
| Development of X-Ray Scanner Using 450-kVp X-Ray Kwak, S.-W.; Kim, K.H.; Kim, I.; Cho, Gyuseong, IEEE Transactions on Nuclear Science, v.50, pp.2414 - 2419, IEEE, 2003-12 |
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