Showing results 3481 to 3540 of 5616
Novel Current Drive Experiments on the CDX-U, HIT, and DIII-D Tokamaks Ono, M; Forest, CB; Hwang, YS; Armstrong, RJ; Choe, Wonho; Darrow, DS; Jones, T, IAEA International Conference on Plasma Physics and Controlled Nuclear Fusion Research, pp.693 - 700, 1992 |
Novel methods for metal artifact reduction in x-ray tomography Cho, Seungryong; Lee, Jung Ryun, International Workshop on Advanced Image Technology (IWAIT), IEEE, 2018-01 |
Novel MoxNbTaxTiZr Medium and High Entropy Alloys for Biomedical Implants-A Systematic Approach to Get a Combination of Mechanical Properties Muhammad, Akmal; Ryu, Ho Jin, 10th Pacific Rim International Conference on Advanced Materials and Processing (PRICM10), PRICM, 2019-08-20 |
Novel Passive Safety Devices for a Sodium-Cooled Fast Reactor: FAST and SAFE Kim, Yonghee; 김치형; 김인형; Hartanto, Donny, ICAPP 2016, ICAPP 2016, 2016-04-18 |
Novel Pwoder Processing for Additive Manufacturing of Metal Matrix Composites Lee, Taegyu; Jeong, Wonjong; CHUNG, SEUNGHYEOK; Ryu, Ho Jin, The International Conference on PROCESSING & MANUFACTURING OF ADVANCED MATERIALS Processing, Fabrication, Properties, Applications (THERMEC 2023), Technische Universitat Wien, 2023-07-06 |
Novel Solid-State Metal Powder Fabrication Process for Feedstock of Metal Matrix Composites Additive Manufacturing Lee, Taegyu; Chung, SeungHyeok; Jeong, Wonjong; Ryu, Ho Jin, The Materials Science & Technology, MS&T 2022, TMS, 2022-10-10 |
NPP Operator Performance Prediction using Facial Expression Analysis 조초우; 성풍현, 한국원자력학회 2019 추계학술발표회, 한국원자력학회, 2019-10-25 |
Nuclear and thermal analysis of shell-fuel pebble design based on the two-temperature homogenized model Yu, H.; Cho, Nam-Zin, 2009 ANS Annual Meeting and Embedded Topical Meeting: Nuclear and Emerging Technologies for Space, NETS 2009, v.100, pp.623 - 626, 2009-06-14 |
Nuclear Data Compression and Reconstruction via Discrete Wavelet Transform Park, Y.R; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.245 - 250, 1997-10 |
Nuclear Decommissioning Policy Implications for Inexperienced Countries SUH, Young A; Yim, Man-Sung, 2017 WM SYMPOSIA, Waste Management, 2017-03-08 |
Nuclear Energy Policy and R&D Prospects: The Korean Case Cho, Nam-Zin, Proc. of the International Conference on the Physics of Reactors:Operation, Design and Computation21, 1996-09 |
Nuclear Facility Access Control Based on Bio-signals to Prevent a Potential Insider Threat Kim, Jung Hwan; Kim, Chul Min; Yim, Man-Sung, INMM 60th Annual Meeting, INSTITUTE OF NUCLEAR MATERIALS MANAGEMENT (INMM), 2019-07-16 |
Nuclear Fuel Cycle Proliferation Resistance Assessment through Direct Coupling with Nuclear Materials Characterization Analysis Steve Skutnik; Yim Man-Sung, Institute of Nuclear Materials Management 2010 Annual Meeting, Institute of Nuclear Materials Management 2010 Annual Meeting, 2010-07 |
Nuclear fuel cycle sensitivity to the variation of physical parameters Scopatz, Anthony M.; Li, Jun; Yim Man-Sung; Schneider, Erich A., International Conference on the Physics of Reactors 2010, PHYSOR 2010, v.3, no.2010, pp.2110 - 2119, PHYSOR, 2010-05 |
Nuclear Fuel Cycle Sensitivity to the Variations of Physical Parameters Anthony Scopatz; Jun Li; Yim Man-Sung; Erich Schneider, PHYSOR 2010 – Advances in Reactor Physics to Power the Nuclear Renaissance, American Nuclear Society, 2010-05 |
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 |
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 |
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 |
Nuclear Program of Korea for Power and Non-power Applications Kang, Hyun Gook, 한국원자력학회 2003 추계학술대회, 한국원자력학회, 2003-10-30 |
Nuclear Proliferation Modeling Method Development 김철민; 임만성; 박현석, 2014 Annual Meeting of INMM-KC, Institute of Nuclear Materials Management - Korea Chapter, 2014-11-13 |
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 |
Nuclear Safety and Public Acceptance Baek, WP; Chang, Soon-Heung, The 7th Nuclear Energy Symposium (NES-7), 2002 |
Nuclear waste management program in Korea: Current status and future Yun, Jong-Il, Migration 09, 2009-09-25 |
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 |
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 |
Numerical Analyses for Reflood Simulation Based on a Mechanistic, Best-Estimate Approach by KREWET Code Chun, Moon Hyun, Proc. of the International Conference on Numerical Methods in Nuclear Engineering, Montreal, Quebec, pp.513 - 529, 1983 |
Numerical Analysis for conductance Probes for the Measurement of Liquid Film Thickness in Two-Phase Flow No, Hee Cheon; Mayinger, F, 한국원자력학회 추계발표회, pp.450 - 455, 1995 |
Numerical Analysis of Break Flow According to Ambient Control Volume Size 신성길; 조재완; 이정익, 2021 한국원자력학회 추계학술발표회, 한국원자력학회, 2021-10-21 |
Numerical Analysis of Characteristics of a Particulate Debris Bed Coolability with Single Phase Flow Lee, J.; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2008-05-29 |
Numerical Analysis of S-CO2 Test Loop Transient Conditions near the Critical Point of CO2 Bae, Seong Jun; Oh, Bongseong; Ahn, Yoonhan; Baik, Seungjoon; Lee, Jekyoung; Lee, Jeong Ik, The Korean Nuclear Society Spring Meeting(2016), The Korean Nuclear Society, 2016-05-12 |
Numerical analysis of single-phase thermal hydraulic parameters along nanostructured coating film Al-Yahia, Omar S; Addad, Yacine; Yoon, Ho Joon; Cho, Sung Oh, International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference, American Society of Mechanical Engineers (ASME), 2020-08 |
Numerical Calibration Method of an Electrochemical Probe for Measurement of Wall-Shear-Stress in Two-Phase Flow No, Hee Cheon; Choi, Ki Yong, 한국원자력학회 춘계발표회, pp.227 - 232, 한국원자력학회, 1996 |
Numerical investigation of a centrifugal compressor for supercritical CO2 as a working fluid Kim, Seong Gu; Ahn, Yoonhan; Lee, Jekyoung; Lee, Jeong-Ik; Addad, Yacine; Ko, Bockseong, ASME Turbo Expo 2014: Turbine Technical Conference and Exposition, GT 2014, American Society of Mechanical Engineers (ASME), 2014-06 |
Numerical Investigation of a Supercritical CO2 Centrifugal Compressor Kim, SG; Lee, J; Ahn, Y; Lee, JeongIk; Addad, Y, ANS 2013 Winter Meeting, ANS, 2013-11-10 |
Numerical simulation of water blast wave mitigation with rubber shield Shin, Young Sik; 김철홍, MARINE 2011, Computational Methods in Marine Engineering IV, MARINE 2011, 2011-09-28 |
Numerical Studies of CO2 Leak Modeling in Sodium-CO2 Heat Exchanger in the SFR coupled with the S-CO2 Brayton Cycle Jung, HY; Lee, Jeong Ik; Wi, MH, NURETH-16(2015), International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2015-08-30 |
Numerical study dual-cycle cardiac 4D CT Y.Lee; Cho, Seungryong, International Forum on Medical Imaging in Asia, IFMI, 2012-11-16 |
Numerical Study for Turbulent Heat Transfer in Helical Wired Sub-channel Flow Regime of Duct-less Assembly in SFR You, Byung-Hyun; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29 |
Numerical Study of UNDEX Nearby Plate with LS-DYNA Shin, Young Sik; Heekyu Woo; Yeon Ok Shin, 81st Shock and Vibration Symposium, SAVIAC, 2010-10-28 |
Numerical Study on the Electrochemical Properties of Ni, Fe, and Cr in Molten LiCl-KCl 윤석주; 최성열, 창립30주년 기념 2020 한국공업화학회 학술대회, 한국공업화학회, 2020-10-30 |
Numerical Study on the Thermal Behavior of Reactor Vessel Lower Head in Ex-Vessel Cooling Yang, SH; Baek,k WP; Chang, Soon-Heung, International Conference on Probabilistic Safety Assessment Methodology and Applications, 1995-01-01 |
NuSEE: An integrated environment of software specification and V&V for NPP safety-critical systems Koo S.R.; Seong P.H.; Cha, Sungdeok, 2005 Annual Meeting - American Nuclear Society, v.92, pp.407 - 408, 2005-06-05 |
Observation of Air Bubble Characteristics by a Vertical Nozzle Under Pool Scrubbing Conditions Yoon, Jongwoong; Jeong, Yong Hoon, The 18th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-18), American Nuclear Society, 2019-08-19 |
Observation of Flow Regime from Bubbly to Jet Flow in the Air Injection Experiment 윤종웅; 정용훈, 2019 한국원자력학회 춘계학술발표회, 한국원자력학회, 2019-05-24 |
OBSERVATION OF HIGH HEAT FLUX BOILING STRUCTURES IN A HORIZONTAL POOL BY A TOTAL REFECTION TECHNIQUE No Hee Cheon; Chu, In-Cheol; Song, Chul-Hwa, NURETH-14, 2011-09 |
Observation of Vortex Entanglement-Disentanglement at the Peak Effect in Nb using Neutron Scattering Park, Sang Ryul; Daniilidis, Nikolaos; Dimitrov, Ivo; Ling, X. S.; Choi, SungMin; Dender, Daniel; Lynn, Jeff, American Physical Society March Meeting, Annual American Physical Society, 2003-03 |
Observation-based CHF model development: Dry spot - Dry patch models No, Hee-Cheon; Ha, Sang-Jun; Chu, In-Cheol; Choi, Jin Young, 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, Association for Computing Machinery, Inc, 2017-09 |
Off Design Performance Map Similarity Study of Radial Type Turbomachinery in Supercritical CO2 Brayton Cycle Cho, Seong Kuk; Lee, Jekyoung; Lee, Jeong-Ik, ASME/JSME/KSME 2015 Joint Fluids Engineering Conference, American Society of Mechanical Engineers, Japan Society of Mechanical Engineers and Korean Society of Mechanical Engineers, 2015-07-29 |
Off design performance of compressors of 150MWe S-CO2 Cycle for Sodium Cooled Fast Reactor Lee, Je Kyoung; Ahn, Yoon Han; Jung, Hwa Young; Kim, Seong Gu; Lee, Jeong Ik, The Korean Nuclear Society Spring Meeting(2014), v.46, The Korean Nuclear Society, 2014-05 |
Off-design Performance Analysis of Compressed CO₂ Energy Storage System Integrated to a Conventional PWR 채용재; 이정익, 2021 한국원자력학회 추계 학술발표회, 한국원자력학회, 2021-10-21 |
Off-design performance prediction of Radial Compressor of Supercritical CO2 Brayton Cycle for KAIST Micro Modular Reactor 조성국; 이제경; 김성구; 이정익, 2014 한국원자력학회 추계학술발표회, 한국원자력학회, 2014-10-31 |
Off-take Experiment at T-junction between Header and Feeder Pipes in CANDU No, Hee Cheon; Hwang, GS; Lee, JY; Moon, YM, NURETH10, 2003 |
Off-take Experiment at T-junction of Surge Line with Upward Branch in Horizontal Pipe No, Hee Cheon; Moon, YM, 2nd Japan-Korea Sym. on Nuclear Thermal Hydraulics and Safety, 2000 |
Off-take Experiment at T-junction of Vertical-Up Branch in the Horizontal Pipe No, Hee Cheon; Moon, YM, Proc. of the Int. Congress on Advanced Nuclear Power Plant, 2002 |
Off-take Experiment at T-junction of Vertical-up Branch on Horizontal Pipe No, Hee Cheon; Moon, Young Min, 한국원자력학회 춘계발표회, 한국원자력학회, 2001 |
OH 분자 방출 스펙트럼을 이용한 상압 플라즈마의 기체온도 측정 문세연; 최원호, pp.312 - 317, 한국물리학회, 2002-06 |
Omni-directional Inductive Power Transfer System for Mobile Robots Using Evenly Displaced Multiple Pick-ups Rim, Chuntaek; Lee, Sungwoo; Cho, Gyu-Hyeong; Choi, Suyong, 2012 IEEE Energy Conversion Congress and Exposition (ECCE), IEEE, 2012-09 |
On a New Acceleration Method for 3D Whole-Core Transport Calculations Cho, Nam-Zin; Lee, G.S; Park, C.J, Annual Meeting of the Atomic Energy Society of Japan, 2003-03 |
On the AFEN Method for Triangular Nodes in Hexagonal Assembly Cores Cho, Nam-Zin; Kim, D.S., Proc. of the Korean Nuclear Society Spring Meeting, pp.25 - 30, 1995-05 |
On the Evaluation of Performance Benefits of Nuclear Waste Transmutation Jun Li; Yim Man-Sung; D. McNelis, Topical Meeting in Accelerator Applications in a Nuclear Renaissance, pp.712 - 722, American Nuclear Society, 2003-06 |
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