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

Showing results 6481 to 6500 of 10287

6481
NUCLEAR FUEL ROD INCLUDING DISK-TYPE BURNABLE ABSORBER

Kim, Yonghee; Jang, seongdong; Nguyen, Xuan Ha

6482
NUCLEAR FUEL ROD INCLUDING DISK-TYPE BURNABLE ABSORBER

Kim, Yonghee; Jang, seongdong; Nguyen, Xuan Ha

6483
Nuclear Hydrogen Production by the SO2 Depolarized Water Electrolysis Using PEMFC

Jung, Yong Hun; Shin, Byung Soo; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2008-10-31

6484
Nuclear nonproliferation and the future expansion of nuclear power

Yim, Man-Sung, PROGRESS IN NUCLEAR ENERGY, v.48, no.6, pp.504 - 524, 2006-08

6485
Nuclear Nonproliferation Culture in South Korea

Choi, Yunhwa; Shin, Da-Hye; Yim, Man-Sung, 2014 Asian Nuclear Prospects Conference, Korea radioactive waste society, 2014-11-11

6486
Nuclear Power Plant Pressurizer Fault Diagnosis Using fuzzy Signed Diagraph Method

Park, Joo Hyun; Seong, Poong-Hyun, International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety, 1994-04

6487
Nuclear power plant pressurizer fault diagnosis using fuzzy signed-digraph and spurious faults elimination methods = 퍼지 SDG 및 의사고장 제거 방법을 이용한 원자력 발전소 가압기의 고장진단에 관한 연구link

Park, Joo-Hyun; 박주현; et al, 한국과학기술원, 1994

6488
Nuclear Power Plant Signal Compression and Reconstruction via Wavelet Transform

Park, Y.R; Cho, Nam-Zin, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.78, pp.212 - 213, 1998

6489
Nuclear Program of Korea for Power and Non-power Applications

Kang, Hyun Gook, 한국원자력학회 2003 추계학술대회, 한국원자력학회, 2003-10-30

6490
Nuclear Proliferation Modeling Method Development

김철민; 임만성; 박현석, 2014 Annual Meeting of INMM-KC, Institute of Nuclear Materials Management - Korea Chapter, 2014-11-13

6491
Nuclear Reactor Thermal Hydraulics (NURETH-10) special issue - part 1 - Foreword

Chang, Soon-Heung; Baek, WP; Rempe, J, NUCLEAR TECHNOLOGY, v.152, no.1, pp.1 - 1, 2005-10

6492
Nuclear Reactor Thermal Hydraulics (NURETH-10) special issue - Part 2 - Foreword

Chang, Soon-Heung; Baek, WP; Rempe, J, NUCLEAR TECHNOLOGY, v.152, no.2, pp.143 - 143, 2005-11

6493
Nuclear Reactor Transient Analysis by Continuous-Energy Monte Carlo Calculation Based on Predictor-Corrector Quasi-Static Method

Jo, Yugwon; Cho, Bumhee; Cho, Nam-Zin, NUCLEAR SCIENCE AND ENGINEERING, v.183, no.2, pp.229 - 246, 2016-06

6494
Nuclear reactor transient analysis via a quasi-static kinetics Monte Carlo method

Jo, Yugwon; Cho, Bumhee; Cho, Nam-Zin, International Conference of Computational Methods in Sciences and Engineering 2015, ICCMSE 2015, American Institute of Physics Inc., 2015-03

6495
Nuclear Safety and Public Acceptance

Baek, WP; Chang, Soon-Heung, The 7th Nuclear Energy Symposium (NES-7), 2002

6496
Nuclear waste management program in Korea: Current status and future

Yun, Jong-Il, Migration 09, 2009-09-25

6497
NUCLEAR-POWER-PLANT PRESSURIZER FAULT-DIAGNOSIS USING FUZZY SIGNED-DIGRAPH AND SPURIOUS FAULTS ELIMINATION METHODS

PARK, JH; Seong, Poong-Hyun, ANNALS OF NUCLEAR ENERGY, v.21, no.6, pp.357 - 369, 1994-06

6498
Nuclear-thermal analysis of a unit fuel element in HTGRs based on two-temperature homogenized model = 두 온도 균질화법에 의한 고온가스로 핵연료요소체의 핵열해석link

Yu, Hui; 유휘; et al, 한국과학기술원, 2010

6499
Nuclear-thermal analysis of coated particle dispersed plate-fuel loaded in a novel research reactor

Lee, Yoonhee; Kim, Yonghee; Cho, Nam-Zin, 2015 ANS Annual Meeting, pp.799 - 802, American Nuclear Society, 2015-06

6500
Nuclear-Thermal Analysis of Fully Ceramic Microencapsulated Fuel via Two-Temperature Homogenized Model

이윤희; 조남진, Proceedings of the Korean Nuclear Society, 한국원자력학회, 2013-10-25

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