Showing results 2601 to 2620 of 10372
Cost savings in nuclear power generating stations by power factor improvement = 역률 개선을 통한 원자력 발전소의 비용절감에 관한 연구link Lee, Young-Seung; 이영승; et al, 한국과학기술원, 2006 |
Cost-benefit Analysis Based on PSA for Additional Passive Safety System and Alternative AC Power Source Kim, Sang Ho; Kang, Hyun Gook; Chang, Soon-Heung; Jeong, Yong Hoon, International Workshop on Nuclear Safety and Severe Accident, The International Atomic Energy Agency, 2014-09-04 |
Cost-Effectiveness Analysis of the New Proposed Fitness-For-Duty (FFD) Evaluation Method 서영아; 임만성, 2018 한국원자력학회 추계학술발표회, 한국원자력학회, 2018-10-25 |
Countercurrent flooding limited critical heat flux in vertical channels at zero inlet flow Park, C; Baek, WP; Chang, Soon-Heung, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.24, no.4, pp.453 - 464, 1997 |
Countercurrent flow limitation in a horizontal pipe connected to an inclined riser No, Hee Cheon; Chun, MH, Trans. of the American Nuclear Society, 1999 |
Coupled Analysis of Passive Safety Injection and Containment Filtered Venting for Passive Decay Heat Removal Kim, Sang Ho; HAM, JAEHYUN; Chang, Soon-Heung; Jeong, Yong Hoon, 2015 International Congress on Advances in Nuclear Power Plants, American Nuclear Society, 2015-05-06 |
Coupled system model analysis for a small modular reactor cogeneration (combined heat and power) application Kang, Seong Woo; Yim, Man-Sung, ENERGY, v.262, 2023-01 |
Coupling Characteristics of a Helicon Antenna in KAIST-Tokamak Plasma Jeon, SJ; Choe, Wonho; Kwon, GC; Kim, JH; Yi, HS; Herr, SW; Chang, HY; et al, in Proc. of the 20th Symposium on Fusion Technology, pp.0 - 327, 1998 |
Coupling of a 2-D Gas Turbine tool with a system analysis code for predicting the transient behavior of the HTGR Kim, Ji Hwan; No, Hee Cheon; Lim, Hong Sik, 한국원자력학회 춘계발표회, 한국원자력학회, 2009 |
Coupling of RELAP5-3D and GAMMA codes for Nuclear Hydrogen System Analysis = 원자력 수소 생산 시스템 분석을 위한 RELAP5-3D와 GAMMA 의 커플링link Jin, Hyung-Gon; 진형곤; et al, 한국과학기술원, 2007 |
Coverage Estimation of Digital Plant Protection System in a Nuclear Power Plant Lee, Jun Seok; Kim, Man Cheol; Seong, Poong-Hyun, 한국원자력학회 2004 추계학술발표대회, 한국원자력학회, 2004-10 |
CPN Based Fault-Tolerance Performance Evaluation of Field Bus for KNGR NPCS Network Jung, Hyun Gi; Seong, Poong-Hyun, 한국원자력학회 '98 추계 학술발표회, pp.92 - 92, 한국원자력학회, 1998-10 |
Cr diffusion coating to improve the corrosion resistance of an ODS steel in super-critical carbon dioxide environment Kim, Chaewon; Kim, Sung Hwan; Cha, Ji-Hwan; Jang, Changheui; Kim, Tae Kyu, SURFACE & COATINGS TECHNOLOGY, v.374, pp.666 - 673, 2019-09 |
Crack-tip plasticity and intrinsic toughening in nano-sized brittle amorphous carbon Shin, Dahye; Jang, Dongchan, INTERNATIONAL JOURNAL OF PLASTICITY, v.127, 2020-04 |
Cracking effect on gamma-ray shielding performance in concrete structure Lee, Chang-Min; Lee, Yoon Hee; Lee, Kun Jai, PROGRESS IN NUCLEAR ENERGY, v.49, no.4, pp.303 - 312, 2007 |
CREAM-based communication error analysis method (CEAM) for nuclear power plant operators communication Lee, Seung Min; Ha, Jun Su; Seong, Poong-Hyun, JOURNAL OF LOSS PREVENTION IN THE PROCESS INDUSTRIES, v.24, no.1, pp.90 - 97, 2011-01 |
Creating a Synthetic Mammogram From a Digital Breast Tomosynthesis Image Hong, Joon Pyo; Cho, Seung Ryong; Lee, Tae Won; Kim, Hyung Seok; Choi, Young Wook, AAPM : 57th Annual Meeting & Exhibition, The American Association of Physicists in Medicine, 2015-07-14 |
Creep and Oxidation Behaviors of Alloy 617 in High Temperature Helium Environments with Various Oxygen Concentrations Koo, Jahyun; Kim, Daejong; Jang, Changheui, Transactions of the Korean Society of Pressure Vessels and Piping, v.7, no.2, pp.34 - 41, 2011-06 |
Creep behavior of Alloy 617 in high temperature air and helium environments-effect of oxidation damage Jang, Changheui; Kim, Sung Hwan; Sah, Injin; Kim, Daejong, JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY, v.30, no.10, pp.4433 - 4438, 2016-10 |
Creep behaviors of alloy 617 at temperatures between 800 and 1000WOC Kim, D.; Jang, Changheui; Ryu, W.S., International Conference on Advances in Nuclear Power Plants, ICAPP 2008, pp.2158 - 2162, 2008-06-08 |
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