Showing results 241 to 300 of 5616
A physics study on alternative reflectors in a compact sodium-cooled breed-and-burn fast reactor Hartanto, Donny; Kim, Yonghee, International Congress on Advances in Nuclear Power Plants: Nuclear Power - A Safe and Sustainable Choice for Green Future, ICAPP 2013, Held with the 28th KAIF/KNS Annual Conference, pp.1754 - 1760, Korean Nuclear Society, 2013-04 |
A pixelated CsI (Tl) scintillator for CMOS-based X-ray image sensor Cha, B.K.; Kim, B.-J.; Cho, Gyuseong; Jeon, S.C.; Bae, J.H.; Chi, Y.K.; Lim, G.-H.; et al, 2006 IEEE Nuclear Science Symposium, Medical Imaging Conference and 15th International Workshop on Room-Temperature Semiconductor X- and Gamma-Ray Detectors, Special Focus Workshops, NSS/MIC/RTSD, pp.1139 - 1143, 2006-10-29 |
A Point Design for a LEU Composite NTP system: Superb Use of Low Enriched Uranium (SULEU) Kim, Yonghee; VENNERI PAOLO, Nuclear and Emerging Technologies for Space, American Nuclear Society, 2016-02-22 |
A Positron Annihilation Study on the Annealing Behavior of Defects in High Purity Titanium 김인섭, Proc. of the Korean Nuclear Society Autumn Meeting, 1994 |
A Potential Way of Co-60 Production in CANDU6 Reactions Kim, Yonghee; Lyu, Jinqi, PBNC 2016, PBNC 2016, 2016-04-06 |
A Practical Review of Studies on Operator’s Supervisory Monitoring Behavior 하준수; 성풍현, 한국원자력학회 2009 춘계학술발표회, 한국원자력학회, 2009-05-21 |
A practical switch-based state-space modeling of DC-DC converters(Part II) Rim, Chuntaek; Cho, G. H., A practical switch-based state-space modeling of DC-DC converters ( Part I ), 1987 |
A preliminary application of the GPS correction to pin-by-pin 2-step PWR depletion Yu, Hwanyeal; Jeong, Hae Sun; Kim, Yonghee, 2019 Transactions of the American Nuclear Society, ANS 2019, pp.1327 - 1330, American Nuclear Society, 2019-11 |
A Preliminary CHF Model Development and Data Comparison with Vertical Heaters under Pool Boiling Conditions 감동훈; 정용훈, 2018 한국원자력학회 춘계학술발표회, 한국원자력학회, 2018-05-18 |
A Preliminary Decay Heat Evaluation for Radwaste from Pyroprocessing of PWR Spent Fuels 이승우; 성풍현, 한국원자력학회 2008 추계학술발표대회, 한국원자력학회, 2008-10-30 |
A Preliminary Experimental Study of Filmwise and Dropwise Condensation on SUS316 Surface Choi, Jae Young; Jeong, Yong Hoon; Watanabe, Noriyuki, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2015-10-30 |
A Preliminary Experimental Study on Flow Boiling CHF Characteristics of Ballooned Channel KIM, YONG JIN; Song, Sub Lee; 문상기; 장순흥, 2013 한국원자력학회 추계학술발표회, 한국원자력학회, 2013-10-24 |
A Preliminary safety analysis of the whole assembly seed-blanket heterogeneous PWR core Lee, JeongIk; Saha,P; Kazimi,MS; Lee,WJ, 12th International Conference on Nuclear Engineering (ICONE12), American Society of Mechanical Engineers, 2004-04-26 |
A Preliminary Study for Development of Amidoxime-functionalized Silica Adsorbents for Uranium(IV) Extraction from Seawater Lee, Min Seok; Ryu, Ho Jin, 한국원자력학회 2016 추계학술대회, 한국원자력학회, 2016-10-27 |
A Preliminary Study for Diffusion Experiments of Metallic Fission Products in Graphite for HTGR Baek, Je Kyun; Mistarihi, Qusai; Yeo, Sunghwan; Lee, Young Woo; Ryu, Ho Jin, 한국원자력학회 2015 추계학술발표회, 한국원자력학회, 2015-10-29 |
A Preliminary Study for Prediction of Supercritical CO2 Compressor Surge Line 조성국; 김성구; 백승준; 이정익, 2017 한국원자력학회 춘계학술발표회, 한국원자력학회, 2017-05-18 |
A Preliminary Study of Burnup Credit Applied to Criticality Analysis of Spent Fuels Kim, Jong Woon; Cho, Nam-Zin; Jang, Hyun-Kie; Choi, Byung-Il; Lee, Heung-Young, Proceedings of International Symposium on Radiation Safety Management (ISRSM 2005), pp.506 - 517, 2005-11 |
A preliminary study of thermal oscillations induced by dryout in printed circuit steam generator (PCSG) Kwon, Jinsu; Lee, Jeong-Ik; Kim, Sang Ji, 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), American Nuclear Society, 2019-08-22 |
A preliminary study on dual-energy computed tomography for small animals Cho, Gyuseong; Chang, Sungho; Ahn, Seong Kyu; Gnarathna, Udana, 2008 Symposium on Radiation Measurements and Applications, 2008 |
A preliminary study on steam generator sizing for the sodium-cooled fast reactor KALIMER-600 권진수; 이정익; 김상지, 2019 한국원자력학회 춘계학술발표회, 한국원자력학회, 2019-05-23 |
A preliminary study on the characteristics of neutron and gamma ray pulse shape discrimination using EJ 276G plastic scintillator 송교혁; 김현덕; 김원구; 최현웅; 박재현; 조규성, 한국원자력학회 춘계학술발표회, 한국원자력학회, 2021-05-13 |
A Preliminary Study on the Radiation Damage to Safeguards Instruments in Head-End Pyroprocess Based on Dose Evaluation 김진환; 조규성, 한국원자력학회, 한국원자력학회, 2017-05-18 |
A Preliminary Study on the Radiation Dose Distribution in the Hot Cell Environment of the Pyroprocess for Safeguards Kim, J; Cho, Gyuseong; Kim, Y; Park, S; Ahn, S, International Pyroprocessing Research Conference 2016, IPRC, 2016-09-22 |
A Preliminary Study on the Radiation Dose Distribution in the Integrated Operation Verification System in the Head-End Hot-Cell of the Pyro-processing Kim, J; Cho, Gyuseong; Ahn, S; Kim, Y; Park, S, 한국원자력학회, 한국원자력학회, 2016-10-27 |
A preliminary study on the radiation dose distribution in the pyroprocess hot cell environment Kim, C; Cho, Gyuseong; Ahn, S; Park, S; Kim, M; Kim, G; Lee, E; et al, 한국원자력학회, 한국원자력학회, 2015-10-29 |
A Preliminary Study on the Resuspension of Radionuclides in Desert Environment Kim, Sung Yeop; Beeley , Philip A.; Chang, Soon-Heung; Yim, Man-Sung, 2014 KNS Annual Spring Conference, Korean Nuclear Society, 2014-05-30 |
A preliminary study on the self-sustainability of a sodium-cooled breed-and-burn fast reactor (B&BR) Hartanto, Donny; Kim, Yonghee, 2015 Transactions of the American Nuclear Society, ANS 2015, pp.1111 - 1114, American Nuclear Society, 2015-11 |
A Probabilistic Approach for the Evaluation of the Control Mode in CREAM 김만철; 성풍현, 한국원자력학회 2003 추계학술발표회, 한국원자력학회, 2003-10 |
A Probabilistic Safety Criterion Based on a Lognormal Distribution of the Public's safety Goals Byong-Whi Lee, Proceedings of the First Korea/Japan Joint Workshop on PSA, 1992 |
A Probabilistic Source Term Model for LLW Performance Assessment Yim Man-Sung; Su Sol-Il; Mu Chen, Transactions of the American Nuclear Society, v.79, no.1998, pp.48 - 50, ANS, 1998-11 |
A Profile-based Method to Select Test Cases for Safety-critical Software 김희은; 손한성; 강현국, KNS 2013 추계학술발표대회, 한국원자력학회, 2013-10-25 |
A Programmable Turbo Decoder for Multiple Third-Generation Wireless Standards Park, In-Cheol; Shin, MC, International Solid-State Circuits Conference, ISCC, 2003-02-13 |
A Proposed Concept of Passive Pressurized Water Reactor Based on Existing Reactor Coolant System Design Chang, S.H; Baek, W.P; Lee, S.W; No, H.C; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.431 - 436, 1992-10 |
A Proposed Design of Collimator and Crystal for Single Photon Detection in Breast Cancer Imaging Kim, KH; Cho, Gyuseong; Lee, W; Chung, TH; Kim, YS; Choi, Y; Kim, S, 한국원자력학회, 2001 |
A Qualitative Study on Low Public Acceptance of Nuclear Power in Terms of Communication Problems Song, Sub Lee; Kim, Sang Ho; Chang, Soon-Heung, 한국원자력학회 춘계학술발표회, 한국원자력학회, 2011-05-26 |
A Quantitative Approach for Human Factors studies in Information Searching Tasks in Nuclear Power Plants Ha, Jun Su; Seong, Poong-Hyun, HCI 2009, 2009-07-20 |
A Quantitative Approach for Risk-Informed Safety Significance Categorization in OPTION-2 Ha, Jun Su; Seong, Poong-Hyun, NUTHOS-6, 2004-10 |
A Quantitative Approach to Modeling the Informaiton Processing of NPP Operators under Input Information Overload Kim, Jong Hyun; Seong, Poong-Hyun, 한국원자력학회 2002 춘계학술발표회, 한국원자력학회, 2002-05 |
A Quantitative Approach to Modeling the Information Processing of NPP Operators under Input Information Overload Kim, Jong Hyun; Seong, Poong-Hyun, Japan-Halden MMS Workshop, pp.46 - 49, 2002-03 |
A Quantitative Approach to Risk-Informed Safety Significance Categorization with an Early Expert Participatory Process Ha, Jun Su; Seong, Poong-Hyun, PSAM, 2004-06 |
A Quantitative Approach to the Information Processing Capacity of Main Control Room Operators in Nuclear Power Plant Kim, Ji Tae; Seong, Poong-Hyun, 대한인간공학회 2006 춘계학술대회, 대한인간공학회, 2006-05-25 |
A Quantitative Assessment Method for the NPP Operators' Diagnosis of Accidents 김만철; 성풍현, 한국원자력학회 2003 춘계학술발표회, pp.96 - 96, 한국원자력학회, 2003-05 |
A Quantitative Assessment Method for Trip Signal Generation Failures 신승기; 성풍현, 한국원자력학회 2010 춘계학술발표대회, 한국원자력학회, 2010-05-28 |
A Quantitative Impact Analysis of Sensor Failures on Human Operator's Decision Making in NPP Seong, Poong-Hyun, NUTHOS-6, 2004-10 |
A quantitative impact analysis of sensor failures on nuclear power plant operators in accident situations Kim, M.C.; Seong, Poong-Hyun, 2005 Annual Meeting - American Nuclear Society, v.92, pp.451 -, 2005-06-05 |
A Quantitative Method for the Fault Coverage of Watchdog Timers in NPP Digital Systems 김만철; 김석준; 성풍현, 한국원자력학회 2003 춘계학술발표회, pp.90 - 90, 한국원자력학회, 2003-05 |
A Quantitative Model of System Man Interaction based on Discrete Function Theory Kim, Man Cheol; Seong, Poong-Hyun, International Seminar on Human-Centered Automation and Software Reliability of Man-Machine Systems from Cognitive Engineering Aspect, pp.101 - 125, 2001-07 |
A Quantitative Model of System Man Interaction Using Discrete Functions 김만철; 성풍현, 한국원자력학회 2001 추계학술발표회, pp.86 - 86, 한국원자력학회, 2001-10 |
A Quick Review on Steam Generator Water Level Tracking Methods and Its Uncertainties Park, Ki Moon; Lee, Jeong-Ik, The Korean Nuclear Society Spring Meeting(2016), The Korean Nuclear Society, 2016-05-12 |
A Rapidly Convergent Generalized Rebalance Method (GRM) for Discrete Ordinates Transport Equations Hong, S.G; Cho, Nam-Zin; Kim, K.S; Song, J.S, Proceedings of the Korean Nuclear Society Spring Meeting, 2007-05 |
A Rebalance Nonlinear Iteration Method for Solving the Neutron Transport Equations Hong, S.G; Cho, Nam-Zin, Proc. of the International Conference on the Physics of Reactors:Operation, Design and Computation376, 1996-09 |
A Refined Mechanistic Critical Heat Flux Model for Upflow Boiling at Low Qualities Lee, KW; Chang, Soon-Heung, The 9th International Heat Transfer Conference, Jerusalem, pp.141 - 146, 1990 |
A Refinement of the Analytic Function Expansion Nodal Method with Interface Flux Moments Woo, S.W; Cho, Nam-Zin; Noh, J.M, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.17 -, 1999 |
A Refinement of the Analytic Function Expansion Nodal Method with Transverse Gradient Basis Functions and Interface Flux Moments Woo, S.W; Cho, Nam-Zin; Noh, J.M, Advances in Reactor Physics and Mathematics and Computation into the Next Millennium (PHYSOR 2000), pp.IX.F.-2 -, 2000-05 |
A Relaiable Feature Matching Method in Omnidirectional Views for Autonomous Map Generation of a Mobile Robot LEE, Young Jin; Chung, Myung Jin, IEEE/RSJ International Conference on Intelligent Robots and Systems, pp.895 - 900, IEEE Robotics and Automation Society (RAS), 2001-11 |
A Reliability Estimation Method for Dynamic Systems Which have Various Operation Modes Varying with Time Seong, Poong-Hyun; Shin, Seung Ki; Jang, Inseok; Kang, Hyun Gook, 8th International Topical Meeting on Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies, pp.308 - 321, ANS, 2012-07-24 |
A Review for Prediction of Supercritical CO2 Compressor Surge Line Cho, Seong Kuk; Kim, Seong Gu; Lee, Jeong-Ik, The 42nd International Technical Conference on Clean Energy, American Public Power Association, 2017-06-13 |
A Review of Various Performance Shaping Factors for Use in Advanced Control Rooms 이승우; 하준수; 박재혁; 김자경; 성풍현, 한국원자력학회 2009 추계학술발표회, 한국원자력학회, 2009-10-29 |
A review on the coupling of CFD code into system code in gas cooled reactor Kim, H.I; No, Hee Cheon, 한국원자력학회 춘계발표회, 한국원자력학회, 2008 |
A review on the coupling of CFD code into system code in gas cooled reactor No, Hee Cheon, KNS 2008 Spring |
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