Browse "NE-Journal Papers(저널논문)" by Type Article
Showing results 301 to 360 of 2827
| An accident diagnosis algorithm using long short-term memory Yang, Jaemin; Kim, Jonghyun, NUCLEAR ENGINEERING AND TECHNOLOGY, v.50, no.4, pp.582 - 588, 2018-05 |
An additional tilted-scan-based CT metal-artifact-reduction method for radiation therapy planning Kim, Changhwan; Pua, Rizza; Lee, Chung-Hwan; Choi, Da-in; Cho, Byungchul; Lee, Sang-wook; Cho, Seungryong; et al, JOURNAL OF APPLIED CLINICAL MEDICAL PHYSICS, v.20, no.1, pp.237 - 249, 2019-01 |
| An Additive Angular-Dependent Rebalance Method for Neutron Transport Equations Cho, Nam-Zin; Park, C.J, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.84, pp.222, 2001 |
| An advanced core design for a soluble-boron-free small modular reactor ATOM with centrally-shielded burnable absorber Nguyen, Xuan Ha; Kim, Chihyung; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.51, no.2, pp.369 - 376, 2019-04 |
| AN ALARM PROCESSING SYSTEM FOR A NUCLEAR-POWER-PLANT USING ARTIFICIAL-INTELLIGENCE TECHNIQUES YANG, JO; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.95, no.3, pp.266 - 271, 1991-09 |
| An analysis of safety-critical digital systems for risk-informed design Kang, Hyun Gook; Sung, T, RELIABILITY ENGINEERING SYSTEM SAFETY, v.78, no.3, pp.307 - 314, 2002-12 |
| An analysis on visual search and EEG during complex diagnostic tasks in NPPs Ha, J.-S.; Seong, Poong-Hyun, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.94, no.0, pp.47 - 48, 2006 |
| An analytic model for situation assessment of nuclear power plant operators based on Bayesian inference Kim, MC; Seong, Poong-Hyun, RELIABILITY ENGINEERING & SYSTEM SAFETY, v.91, no.3, pp.270 - 282, 2006-03 |
| An analytic solution method for discrete ordinates transport equations in slab geometry with no spatial truncation error Hong, S.G; Cho, Nam-Zin, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.81, pp.134 - 136, 1999 |
| An analytical approach to quantitative effect estimation of operation advisory system based on human cognitive process using the Bayesian belief network Lee, Seung Jun; Kim, Man Cheol; Seong, Poong-Hyun, RELIABILITY ENGINEERING & SYSTEM SAFETY, v.93, no.4, pp.567 - 577, 2008-04 |
| An Analytical Approach to the Population Balance Equation for Radioactive Aerosols young ho park; Lee, Kun Jai, ANNALS OF NUCLEAR ENERGY, v.15, no.3, pp.141 - 154, 1988 |
| An application of artificial neural intelligence for personal dose assesment using a multi-area OSL dosimetry system sang-yoon lee; Lee, Kun Jai, RADIATION MEASUREMENTS, v.33, no.3, pp.293 - 304, 2001 |
| An application of dynamic safety system to pressurized water reactor Kim, US; Seong, Poong-Hyun, ANNALS OF NUCLEAR ENERGY, v.25, no.15, pp.1221 - 1233, 1998-09 |
| An application of the dynamic neural network to accident diagnosis systems for nuclear power plants Lee, S.J.; Seong, Poong-Hyun, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.90, no.0, pp.409 - 410, 2004 |
| An Approach to Analyze Diagnosis Errors in Advanced Main Control Room Operations Using the Cause-Based Decision Tree Method Arigi, Awwal Mohammed; Park, Gayoung; Kim, Jonghyun, ENERGIES, v.14, no.13, 2021-07 |
| An assessment methodology for in-vessel corium retention by external reactor vessel cooling during severe accidents in PWRs Park, Jae Hong; Jeong, Yong Hoon; Baek, Won Pil; Chang, Soon Heung, ANNALS OF NUCLEAR ENERGY, v.28, no.12, pp.1237 - 1250, 2001-08 |
| An assessment of the effectiveness of fuel cycle technologies for the national energy security enhancement in the electricity sector Kim, Hyun Jun; Jun, Eunju; Chang, Soon-Heung; Kim, Wonjoon, ANNALS OF NUCLEAR ENERGY, v.36, no.5, pp.604 - 611, 2009-05 |
| An Assessment of the Secondary Neutron Dose in the Passive Scattering Proton Beam Facility of the National Cancer Center Han, Sang Eun; Cho, Gyuseong; Lee, Se Byeong, NUCLEAR ENGINEERING AND TECHNOLOGY, v.49, no.4, pp.801 - 809, 2017-06 |
| An atomically quantized hierarchy of shear transformation zones in a metallic glass Ju, J. D.; Jang, Dongchan; Nwankpa, A.; Atzmon, M., JOURNAL OF APPLIED PHYSICS, v.109, no.5, 2011-03 |
| An Automatic Optimal Fuel Management Method for CANDU 6 Reactors Jeong, C.J; Cho, Nam-Zin; Choi, H.B, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.84, pp.207, 2001 |
| AN AXIOMATIC DESIGN APPROACH OF NANOFLUID-ENGINEERED NUCLEAR SAFETY FEATURES FOR GENERATION III plus REACTORS Bang, In Cheol; Heo, Gyunyoung; Jeong, Yong Hoon; Heo, Sun, NUCLEAR ENGINEERING AND TECHNOLOGY, v.41, no.9, pp.1157 - 1170, 2009-11 |
| An effective technique for the software requirements analysis of NPP safety-critical systems, based on software inspection, requirements traceability, and formal specification Koo, SR; Seong, Poong-Hyun; Yoo, J; Cha, Sungdeok; Yoo, YJ, RELIABILITY ENGINEERING & SYSTEM SAFETY, v.89, no.3, pp.248 - 260, 2005-09 |
| An efficient deterministic method for generating non-negative scattering cross-sections Kim, Jong Woon; Cho, Nam-Zin, ANNALS OF NUCLEAR ENERGY, v.34, no.12, pp.967 - 976, 2007-12 |
| An empirical study of the personality effects on diagnosis performance of human operators in unexpected plant conditions of NPPs Kim, Tae Jin; Lee, Chanyoung; Kang, Seong Keun; Choi, Moon Kyoung; Seong, Poong Hyun, ANNALS OF NUCLEAR ENERGY, v.145, 2020-09 |
| An empirical study on the basic human error probabilities for NPP advanced main control room operation using soft control Jang, Inseok; Kim, Ar Ryum; Al Harbi, Mohamed Ali Salem; Lee, Seung Jun; Kang, Hyun Gook; Seong, Poong-Hyun, NUCLEAR ENGINEERING AND DESIGN, v.257, pp.79 - 87, 2013-04 |
| An empirical study on the human error recovery failure probability when using soft controls in NPP advanced MCRs Jang, Inseok; Kim, Ar Ryum; Jung, Wondea; Seong, Poong-Hyun, ANNALS OF NUCLEAR ENERGY, v.73, pp.373 - 381, 2014-11 |
| An empirical study on the relationships between functional performance measure and task performance measure in NPP MCR Jang, Inseok; Park, Jinkyun; Seong, Poonghyun, ANNALS OF NUCLEAR ENERGY, v.42, pp.96 - 103, 2012-04 |
| AN EXAMINATION OF SIMPLIFICATION AND UNCERTAINTY ON MATERIAL ATTRACTIVENESS EVALUATION FOR PROLIFERATION RESISTANCE ASSESSMENT Skutnik, Steven E.; Yim, Man-Sung, NUCLEAR TECHNOLOGY, v.179, no.3, pp.374 - 381, 2012-09 |
| An experimental approach to estimate operator's information processing capacity for diagnosing tasks in NPPs Kim, Ji-Tae; Shin, Seung-Ki; Kim, Jong-Hyun; Seong, Poong-Hyun, ANNALS OF NUCLEAR ENERGY, v.59, pp.100 - 110, 2013-09 |
| An experimental approach to estimation of human information processing capacity Kim, J.T.; Seong, Poong-Hyun, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.95, no.0, pp.928 - 929, 2006 |
| An experimental investigation on relationship between PSFs and operator performances in the digital main control room Park, Jooyoung; Lee, Daeil; Jung, Wondea; Kim, Jonghyun, ANNALS OF NUCLEAR ENERGY, v.101, pp.58 - 68, 2017-03 |
| An experimental investigation on the critical heat flux enhancement by mechanical vibration in vertical round tube Lee, YH; Kim, DH; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.229, no.1, pp.47 - 58, 2004-04 |
| An experimental investigation on the relationship between effectiveness in information searching and situation awareness during complex diagnostic tasks in NPPs Ha, J.-S.; Seong, Poong-Hyun, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.98, no.0, pp.76 - 77, 2008 |
| An experimental observation of the effects of submicron- and micron-sized mesoporous silica particles on the critical heat flux Lee, Min Suk; Kam, Dong Hoon; Jeong, Yong Hoon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.160, pp.120182, 2020-10 |
| An Experimental Study of the Pool-Boiling CHF on Downward-Facing Plates Yang, Soo-Hyung; Baek, Won-Pil; Chang, Soon-Heung, NUCLEAR ENGINEERING AND TECHNOLOGY , v.26, no.4, pp.493 - 501, 1994-04 |
| An experimental study of thermal-hydraulic phenomena in the downcomer with a direct vessel injection system of APR1400 during the LBLOCA reflood phase Lee, DW; No, Hee Cheon; Kim, HG; Oh, SJ, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.41, no.4, pp.440 - 447, 2004-04 |
| AN EXPERIMENTAL STUDY ON AIR-WATER COUNTERCURRENT FLOW LIMITATION IN THE UPPER PLENUM WITH A MULTI-HOLE PLATE SONG, CHUL-HWA; NO, HEECHEON; LEE, KYUNG-WON, NUCLEAR ENGINEERING AND TECHNOLOGY, v.37, no.6, pp.557 - 564, 2005-12 |
| An experimental study on CHF enhancement in flow boiling using Al2O3 nano-fluid Kim, Tae-Il; Jeong, Yong-Hoon; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.53, no.5-6, pp.1015 - 1022, 2010-02 |
| An experimental study on CHF enhancement of wire nets covered surface in R-134a flow boiling under high pressure and high mass flux conditions Song, Sub Lee; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.90, pp.761 - 768, 2015-11 |
| An experimental study on CHF in pool boiling system with SA508 test heater under atmospheric pressure Lee, Juno; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.250, pp.720 - 724, 2012-09 |
| An Experimental Study on Factors Affecting the Leachability of Cs-137 in Cement Matrix and Leaching Model with Backfill jong-kil park; kun jai lee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.23, no.4, pp.374 - 386, 1991 |
| An Experimental Study on the Characteristics of Electromagnetic Filter geum-young lee; seung-cheol lim; kun jai lee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.25, pp.178 - 191, 1993 |
| An iDTMC-based Monte Carlo depletion of a 3D SMR with intra-pin flux renormalization Kim, Inhyung; Kim, Inyup; Kim, Yonghee, FRONTIERS IN ENERGY RESEARCH, v.10, 2022-08 |
| An Image-Based Reduction of Metal Artifacts in Computed Tomography Pua, Rizza; WI, Sunhee; Park, Miran; Lee, Jung-Ryun; Cho, Seungryong, JOURNAL OF COMPUTER ASSISTED TOMOGRAPHY, v.40, no.1, pp.131 - 141, 2016-01 |
| An impact analysis of human machine interface with autonomous operating system on nuclear power plant system safety Lee, S.J.; Kim, M.C.; Kim, U.S.; Seong, Poong-Hyun, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.88, no.1, pp.33</div> - 33</div>, 2003 |
| An improved deterministic truncation of Monte Carlo solution for pin-resolved nuclear reactor analysis Kim, Inhyung; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.166, 2022-02 |
| An Improved Mechanistic Model to Predict Critical Heat Flux in Subcooled and Low Quality Convective Boiling Kwon, Young Min; Chang, Soon-Heung, NUCLEAR ENGINEERING AND TECHNOLOGY, v.31, no.2, pp.236 - 255, 1999-04 |
| An improved method for reactor coolant pump abnormality monitoring using power line signal analysis Jung, JC; Seong, Poong-Hyun, NUCLEAR ENGINEERING AND DESIGN, v.236, no.1, pp.57 - 62, 2006-01 |
| AN IMPROVED MONTE CARLO METHOD APPLIED TO THE HEAT CONDUCTION ANALYSIS OF A PEBBLE WITH DISPERSED FUEL PARTICLES Song, Jae Hoon; Cho, Nam-Zin, NUCLEAR ENGINEERING AND TECHNOLOGY, v.41, no.3, pp.279 - 286, 2009-04 |
| AN IMPROVED NUMERICAL SCHEME WITH THE FULLY-IMPLICIT 2-FLUID MODEL FOR A FAST-RUNNING SYSTEM CODE JEONG, JJ; No, Hee Cheon, NUCLEAR ENGINEERING AND DESIGN, v.104, no.2, pp.145 - 153, 1987-10 |
| An improved physical model for flooding limited CHF under zero and very low flow conditions Park, C; Hwang, DH; Chang, Soon-Heung; Baek, WP, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.25, no.3, pp.339 - 348, 1998-04 |
| An improved RELAP5/MOD3.3 reflood model considering the effect of spacer grids Choi, Tong Soo; No, Hee Cheon, NUCLEAR ENGINEERING AND DESIGN, v.250, pp.613 - 625, 2012-09 |
| An in-situ Raman spectroscopic study on potential-pO2-phase diagram of lanthanum in LiCl-KCl eutectic melt Park, Seung; Yun, Jong-Il, JOURNAL OF RARE EARTHS, v.38, no.7, pp.793 - 800, 2020-07 |
| An independent assessment of Groeneveld et al.s 1995 CHF look-up table Baek, WP; Kim, HC; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.178, no.3, pp.331 - 337, 1997-12 |
| An Informantion Theory-based Approach to Modeling the Information Processing of NPP Operators Kim, JongHyun; Seong, PoongHyun, NUCLEAR ENGINEERING AND TECHNOLOGY , v.34, no.4, pp.301 - 313, 2002-08 |
| An information theory-based approach for quantitative evaluation of user interface complexity Kang, Hyun Gook; Seong, Poong-Hyun, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.45, no.6, pp.3165 - 3174, 1998-12 |
| An innovative core design for a soluble-boron-free small pressurized water reactor Yahya, Mohd Syukri; Kim, Yonghee, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.42, no.1, pp.73 - 81, 2018-01 |
| An innovative method to reduce count loss from pulse pile-up in a photon-counting pixel for high flux X-ray applications Lee, D.; Lim, Kyung Taek; Park, K.; Lee, C.; Alexander, S.; Cho, Gyuseong, JOURNAL OF INSTRUMENTATION, v.12, 2017-03 |
| An integral equation model for critical heat flux at subcooled and low quality flow boiling Chun, TH; Baek, WP; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.199, no.1-2, pp.13 - 29, 2000-06 |
| An integral response scaling method for reduced-height test facilities and its validation using RELAP5 for loss of RHR during midloop operation Kim, HT; No, Hee Cheon, NUCLEAR TECHNOLOGY, v.136, no.2, pp.169 - 185, 2001-11 |
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Open Access
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- 516 2020 - 2024
- 1,120 2010 - 2019
- 712 2000 - 2009
- 369 1990 - 1999
- 110 1980 - 1989