Browse "NE-Journal Papers(저널논문)" by Type Article
Showing results 2101 to 2160 of 2827
| Plasticity of indium nanostructures as revealed by synchrotron X-ray microdiffraction Budiman, Arief Suriadi; Lee, Gyuhyon; Burek, Michael J.; Jang, Dongchan; Han, Seung Min J.; Tamura, Nobumichi; Kunz, Martin; et al, MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, v.538, pp.89 - 97, 2012-03 |
| Polar-coordinate-based data analysis scheme for high-voltage measurement system using the Pockels electro-optic effect Choi, S.; Sugianto, A. A.; Lee, D-G; Woo, H. J.; Hong, S. H.; Ghim, Young-chul, JOURNAL OF INSTRUMENTATION, v.15, no.3, 2020-03 |
| Polarization-modulated magnetic soft-x-ray transmission microscopy Anderson, E; Fischer, P; Cho, Gyuseong; Kang, BS; Kim, DH, JOURNAL OF APPLIED PHYSICS, v.98, no.9, pp.869 - 888, 2005-11 |
| Polycrystalline cubic boron nitride sintered compacts prepared from nanocrystalline TiN coated cBN powder Umer, Malik Adeel; Sub, Park Hee; Lee, Dong Ju; Ryu, Ho Jin; Hong, Soon Hyung, MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, v.552, pp.151 - 156, 2012-08 |
| Polydispersed Colloid Transport in Porous Media : An Experiment and Modelling 최희주; 이건재, 한국원자력학회지, v.27, no.1, pp.1 - 7, 1995-02 |
| Polymerized rodlike nanoparticles with controlled surface charge density Kim, TH; Choi, SungMin; Kline, SR, LANGMUIR, v.22, no.6, pp.2844 - 2850, 2006-03 |
| Polynomial relaxation in the quasi-static approach and its implementation in nonlinear reactor transient analyses Oh, Tae-suk; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.158, 2021-08 |
| Pool-boiling critical heat flux of water on small plates: Effects of surface orientation and size Yang, SH; Baek, WP; Chang, Soon-Heung, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.24, no.8, pp.1093 - 1102, 1997-12 |
| Porous Silica-Coated Gold Sponges with High Thermal and Catalytic Stability Lee, Min-Jae; Kang, Shin Hyun; Dey, Jahar; Choi, Sung-Min, ACS APPLIED MATERIALS & INTERFACES, v.10, no.26, pp.22562 - 22570, 2018-07 |
| Possible power increase in a natural circulation Soluble-Boron-Free Small Modular Reactor using the Truly Optimized PWR lattice Wijaya, Steven; Nguyen, Xuan Ha; Kim, Yonghee, NUCLEAR ENGINEERING AND TECHNOLOGY, v.55, no.1, pp.330 - 338, 2023-01 |
| Post-Cold War civilian nuclear cooperation and implications for nuclear nonproliferation Nguyen, Viet Phuong; Yim, Man-Sung, PROGRESS IN NUCLEAR ENERGY, v.93, pp.246 - 259, 2016-11 |
| Post-decontamination treatment of MXene after adsorbing Cs from contaminated water with the enhanced thermal stability to form a stable radioactive waste matrix ul Hassan, Muhmood; Lee, Sujeong; Mehran, Muhammad Taqi; Shahzad, Faisal; Husnain, Syed M.; Ryu, Ho Jin, JOURNAL OF NUCLEAR MATERIALS, v.543, 2021-01 |
| POST-IRRADIATION ANALYSES OF U-MO DISPERSION FUEL RODS OF KOMO TESTS AT HANARO Ryu, Ho Jin; Park, J. M.; Jeong, Y. J.; Lee, K. H.; Lee, Y. S.; Kim, C. K.; Kim, Y. S., NUCLEAR ENGINEERING AND TECHNOLOGY, v.45, no.7, pp.847 - 858, 2013-12 |
| Potential advantages of coupling supercritical CO2 Brayton cycle to water cooled small and medium size reactor Yoon, Ho Joon; Ahn, Yoonhan; Lee, Jeong Ik; Addad, Yacine, NUCLEAR ENGINEERING AND DESIGN, v.245, pp.223 - 232, 2012-04 |
| Potential improvements of supercritical recompression CO(2) Brayton cycle by mixing other gases for power conversion system of a SFR Jeong, Woo Seok; Lee, JeongIk; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND DESIGN, v.241, no.6, pp.2128 - 2137, 2011-06 |
| Potential of FAST (floating absorber for safety at transient) as a solution for positive coolant temperature coefficient in sodium-cooled FAST reactors Kim, Chihyung; Kim, Yonghee, ANNALS OF NUCLEAR ENERGY, v.137, 2020-03 |
| Potential sodium-CO2 interaction of a supercritical CO2 power conversion option coupled with an SFR: Basic nature and design issues Eoh, Jae-Hyuk; No, Hee Cheon; Lee, Yong-Bum; Kim, Seong-O, NUCLEAR ENGINEERING AND DESIGN, v.259, pp.88 - 101, 2013-06 |
| Potentiodynamic polarization behaviour of AISI type 316 stainless steel in NaCl solution Yi, Y.; Cho, P.; Al Zaabi, A.; Addad, Y.; Jang, Changheui, CORROSION SCIENCE, v.74, pp.92 - 97, 2013-09 |
Powder Metallurgy Processing of a WxTaTiVCr High-Entropy Alloy and Its Derivative Alloys for Fusion Material Applications Waseem, Owais Ahmed; Ryu, Ho Jin, SCIENTIFIC REPORTS, v.7, 2017-05 |
| Power maneuvering of pressurized water reactors with axially variable strength control rods Kim, US; Seong, Poong-Hyun, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.51, no.1, pp.267 - +, 2004-02 |
| Power mapping in a Canada Deuterium Uranium reactor using Kalman filtering technique Jeong, CJ; Cho, Nam-Zin, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.37, no.9, pp.758 - 768, 2000-09 |
| POWER PREDICTION IN NUCLEAR-POWER-PLANTS USING A BACK-PROPAGATION LEARNING NEURAL NETWORK ROH, MS; CHEON, SW; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.94, no.2, pp.270 - 278, 1991-05 |
| Practical switch based state-space modeling of DC-DC converters with all parasitics Rim, Chuntaek; Joung, Gyu B.; Cho, Gyu-Hyeong, IEEE TRANSACTIONS ON POWER ELECTRONICS, v.6, no.4, pp.611 - 617, 1991-10 |
| Prediction of Ce (III) Electrodeposition at Various Electrochemical Conditions in Molten LiCl-KCl Eutectic Jee, YoungTaek; Yun, Jong-Il, ECS TRANSACTIONS, v.85, no.4, pp.33 - 40, 2018-04 |
| Prediction of Critical Heat Flux for Saturated Flow Boiling Water in Vertical Narrow Rectangular Channels Choi, Gil Sik; Chang, Soon-Heung; Jeong, Yong Hoon, Transactions of the Korean Society of Mechanical Engineers, B, v.39, no.12, pp.953 - 963, 2015-12 |
| Prediction of Fatal Radiation-Induced Cancer for Korean Using the BEIR V Method Hwang, Won-Tae; Han, Moon-Hee; Cho, Gyu-Seong, 방사선방어학회지 , v.21, no.3, pp.175 - 182, 1997-06 |
| Prediction of inner pinch for supercritical CO2 heat exchanger using Artificial Neural Network and evaluation of its impact on cycle design Son, Seongmin; Heo, Jin Young; Lee, Jeong-Ik, ENERGY CONVERSION AND MANAGEMENT, v.163, pp.66 - 73, 2018-05 |
| Prediction of Safety Critical Software Operational Reliability from Test Reliability Using Environment Factors Jung, Hoan-Sung; Seong, Poong-Hyun, NUCLEAR ENGINEERING AND TECHNOLOGY , v.31, no.1, pp.49 - 57, 1999-02 |
| PREDICTION OF SEVERE ACCIDENT OCCURRENCE TIME USING SUPPORT VECTOR MACHINES Kim, Seung Geun; No, Young Gyu; Seong, Poong-Hyun, NUCLEAR ENGINEERING AND TECHNOLOGY, v.47, no.1, pp.74 - 84, 2015-02 |
| Prediction of Software Operational Reliability Using Testing Environment Factors Jung, HS; Seong, Poong-Hyun, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.73, pp.143 - 146, 1995 |
| Prediction of the critical heat flux for saturated upward flow boiling water in vertical narrow rectangular channels Choi, Gil Sik; Chang, Soon Heung; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND DESIGN, v.303, pp.1 - 16, 2016-07 |
| Prediction of the Fundamental Mode Lamb Wave Reflection from a Crack-Like Discontinuity Using Eigen-Mode Expansion 박재석; 장창희; 이종포, 비파괴검사학회지, v.30, no.3, pp.194 - 199, 2010-06 |
| Prediction of the human response time with the similarity and quantity of information Lee, S; Heo, G; Chang, Soon-Heung, RELIABILITY ENGINEERING & SYSTEM SAFETY, v.91, no.6, pp.728 - 734, 2006-06 |
| Prediction of the Volume of Solid Radioactive Wastes to be Generated from Korean Next Generation Reactor Cheong, Jae-Hak; Lee, Kun-Jai; Maeng, Sung-Jun; Song, Myung-Jae; Park, Kyu-Wan, 원자력학회지, v.29, no.3, pp.218 - 228, 1997 |
| Preliminary conceptual design and cost estimation for Korea Advanced Pyroprocessing Facility Plus (KAPF plus ) Ko, Won Il; Lee, Ho Hee; Choi, Sungyeol; Kim, Sung-Ki; Park, Byung Heung; Lee, Hyo Jik; Kim, In Tae; et al, NUCLEAR ENGINEERING AND DESIGN, v.277, pp.212 - 224, 2014-10 |
| Preliminary conceptual design and cost estimation for SFR Fuel Manufacturing Facility (SFMF) Ko, Won Il; Lee, Ho Hee; Choi, Sungyeol; Kim, Ki Hwan; Kim, Sung-Ki; Park, Byung Heung; Lee, Hyo Jik; et al, NUCLEAR ENGINEERING AND DESIGN, v.277, pp.225 - 233, 2014-10 |
| Preliminary conceptual design of a new moderated reactor utilizing an LEU fuel for space nuclear thermal propulsion Nam, Seung Hyun; Venneri, Paolo; Kim, Yonghee; Chang, Soon Heung; Jeong, Yong Hoon, PROGRESS IN NUCLEAR ENERGY, v.91, pp.183 - 207, 2016-08 |
| Preliminary design of a helium cooled molten lithium test blanket module for the ITER test in Korea Lee, Dong Won; Hong, Bong Geun; Kim, Yonghee; In, Wang Ki; Yoon, Kyung Ho, FUSION ENGINEERING AND DESIGN, v.82, no.4, pp.381 - 388, 2007-06 |
| Preliminary design of safety system using phase change material for passively cooling of nuclear reactor containment building Shin, Sung Gil; Cho, Jai Oan; Ko, Areum; Jung, Hwa-Young; Lee, Jeong Ik, APPLIED THERMAL ENGINEERING, v.200, pp.117672, 2022-01 |
| Preliminary design of the soft x-ray array tomographic diagnostic system for Korea Superconducting Tokamak Advanced Research (KSTAR) plasmas Kim, J; Choe, Wonho, REVIEW OF SCIENTIFIC INSTRUMENTS, v.75, pp.3974 - 3976, 2004-10 |
| Preliminary feasibility study of PCM condenser for PCCS of APR1400 Cho, Jai Oan; Ko, Areum; Shin, Sung Gil; Jung, Hwa-Young; Lee, Jeong Ik, ANNALS OF NUCLEAR ENERGY, v.152, pp.107959, 2021-03 |
| Preliminary result of an advanced tangential X-ray pinhole camera system with a duplex MWPC on KSTAR plasma Jang, Siwon; Lee, Sang Gon; Lim, Chang Hwy; Kim, Hyun Ok; Kim, Sang Yeol; Lee, Seung Hun; Hong, Joohwan; et al, CURRENT APPLIED PHYSICS, v.13, no.5, pp.819 - 825, 2013-07 |
| Preliminary safety analysis of Korea Helium Cooled Solid Breeder Test Blanket Module Ahn, Mu-Young; Cho, Seung-Yon; Kim, Duck-Hoi; Lee, Eun-Seok; Kim, Hyung-Seok; Suh, Jae-Seung; Yun, Sung-Hwan; et al, FUSION ENGINEERING AND DESIGN, v.83, no.10-12, pp.1753 - 1758, 2008-12 |
| Preliminary studies of compact Brayton cycle performance for Small Modular High Temperature Gas-cooled Reactor system Bae, Seong Jun; Lee, Jekyoung; Ahn, Yoonhan; Lee, Jeong-Ik, ANNALS OF NUCLEAR ENERGY, v.75, pp.11 - 19, 2015-01 |
| Preliminary study of applying adjoint-based mesh optimization method to nuclear power plant safety analysis Son, Seongmin; Lee, Jeong-Ik, ANNALS OF NUCLEAR ENERGY, v.109, pp.405 - 418, 2017-11 |
| Preliminary study on a new self-sealing strategy for nuclear reactor containment buildings using phase change materials Choi, Yonadan; Jung, Jun Yeong; Lee, Min Suk; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND DESIGN, v.402, 2023-02 |
| Preparation and characterization of magnetic nanoparticles and their silica egg-yolk-like nanostructures: A prospective multifunctional nanostructure platform Chen, Minghai; Kim, Yong-Nam; Li, Cuncheng; Cho, Sung-Oh, JOURNAL OF PHYSICAL CHEMISTRY C, v.112, no.17, pp.6710 - 6716, 2008-05 |
| PRESSURE-DROP AND INTERFACE DRAG COEFFICIENT IN 2-PHASE FLOW OF SODIUM No, Hee Cheon; KAZIMI, MS, NUCLEAR SCIENCE AND ENGINEERING, v.82, no.3, pp.235 - 242, 1982 |
| Pressurized thermal shock analyses of a reactor pressure vessel using critical crack depth diagrams Jhung, MJ; Park, YW; Jang, Changheui, INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, v.76, no.12, pp.813 - 823, 1999-10 |
| PRESSURIZED WATER-REACTOR CORE PARAMETER PREDICTION USING AN ARTIFICIAL NEURAL NETWORK KIM, HG; Chang, Soon-Heung; LEE, BH, NUCLEAR SCIENCE AND ENGINEERING, v.113, no.1, pp.70 - 76, 1993-01 |
| Probabilistic Analysis of Allowed Outage Times Relaxation at a PWR Plant Cho, Nam-Zin; Chu, T; Xue, D; Bozoki, G; Youngblood, R, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.53, pp.349, 1986 |
| Probabilistic Fracture Mechanics Round Robin Analysis of Reactor Pressure Vessels during Pressurized Thermal Shock Jhung, Myung Jo; Kim, Seok Hun; Choi, Young Hwan; Chang, Yoon Suk; Xu, Xiangyuan; Kim, Jong Min; Kim, Jong Wook; et al, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.47, no.12, pp.1131 - 1139, 2010-12 |
| Probabilistic risk assessment of aircraft impact on a spent nuclear fuel dry storage Al Momani, Bela; Lee, Sanghoon; Jang, Dongchan; Kang, Hyun Gook, NUCLEAR ENGINEERING AND DESIGN, v.311, pp.104 - 119, 2017-01 |
| PROBABILISTIC RISK ASSESSMENT OF NUCLEAR WASTE REPOSITORY WITH THE MECHANISTICALLY MODELED FAILURE RATE CHO, WJ; Chang, Soon-Heung, RADIOACTIVE WASTE MANAGEMENT AND ENVIRONMENTAL RESTORATION, v.15, no.4, pp.203 - 220, 1991 |
| Probabilistic Safety Assessment for High Level Nuclear Waste Repository System tae-woon kim; kap-koo woo; kun jai lee, 방사선방어학회지, v.16, no.1, pp.53 - 72, 1991 |
| Probability of Vessel Failure during PTS Transient with Repressurization 정명조; 장창희; 최영환, Transactions of the Korean Society of Pressure Vessels and Piping, 2008-04 |
| Probe area effect on performance of phoswich detectors for simultaneous alpha and beta detection Kim, W.; Kim, J.; Ko, Kilyoung; Kim, G.; Cho, Gyuseong, JOURNAL OF INSTRUMENTATION, v.14, no.10, 2019-10 |
| Probing plasmas with ion acoustic waves Hershkowitz, Noah; Ghim, Young-chul, PLASMA SOURCES SCIENCE TECHNOLOGY, v.18, no.1, 2009-02 |
| PROCEDURE FOR APPLICATION OF SOFTWARE RELIABILITY GROWTH MODELS TO NPP PSA Son, Han Seong; Kang, Hyun Gook; Chang, Seung Cheol, NUCLEAR ENGINEERING AND TECHNOLOGY, v.41, no.8, pp.1065 - 1072, 2009-10 |
| Progress in gyrokinetic validation studies using NBI heated L-mode discharge in KSTAR Kim, D; Kang, J; Lee, MW; Candy, J; Yoon, ES; Yi, S; Kwon, JM; et al, CURRENT APPLIED PHYSICS, v.42, pp.60 - 70, 2022-10 |
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