Showing results 4761 to 4780 of 5608
The role of humic acid on the formation of hydroxy-aluminosilicate colloid-borne actinides Priemyshev, A.; Breban, D.; Kim, M. A.; Panak, P.J.; Mansel, A.; Yun, Jong-Il; Kim, J.I.; et al, International Conference on Chemistry and Migration Behavior of Actinides and Fission Products in the Geosphere (Migration '05), 2005-09 |
The role of humic acid on the formation of hydroxy-aluminosilicate colloid-borne actinides Priemyshev, A.; Breban, D.; Kim, M.A; Panak, P.J.; Mansel, A.; Yun, Jong-Il; Kim, J.I.; et al, GdCh-Jahrestagung Chemie 2005, 2005-09 |
The roles of transport partial current information in two-level p-CMFD acceleration in the whole-core transport calculation Cho, Nam-Zin, Transactions of the American Nuclear Society, ANS 2019, pp.1323 - 1326, American Nuclear Society, 2019-11 |
The Scaling Effect on the Critical Heat Flux of a Downward Curved Flow Channel Park, Hae Min; Jeong, Yong Hoon, The 18th Pacific Basin Nuclear Conference(PBNC 2012), KAIF,KNS, 2012-05 |
The self-discharge behaviors of lithium/sulfur cells with tetra(ethylene glycol) dimethyl ether[TEGDME] as electrolyte Ryu H.S.; Kim K.W.; Ahn J.H.; Lee, Jai Young; Cho K.K.; Hur B.Y.; Ahn H.J., 205th Electrochemical Society Fall Meeting, pp.380 - 385, 2003-10-12 |
The sensitivity of repository capacity to the separation efficiency of TRUs and fission products Li, Jun; Yim, Man-Sung; McNelis, David N., 2009 ANS Annual Meeting and Embedded Topical Meeting: Nuclear and Emerging Technologies for Space, v.100, no.2009, pp.180 - 182, ANS, 2009-06 |
The Sensitivity of Repository Capacity to the Separation Efficiency of TRUs and Fission Products Jun Li; Yim Man-Sung; David McNelis, Transactions of the American Nuclear Society, v.100, no.2009, pp.180 - 182, American Nuclear Society, 2009-06 |
The Sintering Behavior of Gd2O3 and Characteristics of Metal Matrix Composite Reinforced with the Sintered Gd2O3 Lee, TaeGyu; Ryu, Ho Jin; Moon, JiWon, The 3rd Asian Nuclear Fuel Conference (ANFC-2017), Asian Nuclear Fuel Conference, 2017-09-08 |
The Solubility of Magnetite and Nickel Ferrite in Aqueous Solutions Lee, Kun Jai, 1988 JAIF Int'l Conference on Water Chemistry in Nuclear Power Plants, pp.744 - 749, 1988 |
The Specific Temperature Increase Method for Repository Thermal Analysis Jun Li; Yim Man-Sung; David McNelis, Transactions of the American Nuclear Society, v.99, no.2008, pp.216 - 218, American Nuclear Society, 2008-11 |
The Statistical Analysis for the Characteristics of Low-Level Wastes Generated from PWR Lee, Kun Jai, Waste Management '91, pp.329 - 335, 1991 |
The Statistical Analysis for the Characteristics of Low-Level Wastes Generated from PWR 이건재, 한국원자력학회 학술발표회 ( 춘계 ), pp.505 - 524, 1991 |
The Study of the Gamma Energy Identifying Algorithm with the Noise Reduction Method for a Compact Radiation Sesnsor Yoo, H; Cho, Gyuseong; Kim, Y; Kim, M; Lim, Kyung Taek, IEEE Symposium On Radiation Measurements and Applications, IEEE Symposium On Radiation Measurements and Applications, 2016-05-25 |
The Study on the Magnetic Filter using the Rotation of Permanent Magnets for Separation of Radioactive Corrosion Products Lee, Kun Jai, Symposium on Water Chemistry and Corrosion in Nuclear Power Plants in Asia 2003, 2003 |
The Synergetic Effects of a Nuclear-Assisted Gas Turbine Power Cycle Jeong, Yong Hoon; Saha, Pradip; Kazimi, Mujid S., American Nuclear Society 2004 Winter Meeting, 2004-11-14 |
The Synthesis and Analysis of WxTaTiVCr Alloy for High Temperature and Plasma Facing Applications Waseem, Owais Ahmed; Ryu, Ho Jin; Kim, Seung Su; Hong, Soon Hyung, The Nuclear Materials Conference, Elsvier, 2016-11-08 |
The Synthesis and Characterization of W- 1wt. % TiC Alloy Using a Chemical Method Ryu, Ho Jin; Kim, Tae Hee, 한국분말야금학회 2016 추계학술대회, 한국분말야금학회, 2016-11-10 |
The Transient Thermal Analysis at a Nuclear Containment Wall during LOCA for an Analysis of a PCM Behavior 최요나단; 정용훈, 2020 한국원자력학회 춘계학술발표회, 한국원자력학회, 2020-07-09 |
The Two Step Characteristic Method to Reduce Numerical Diffusion Golay, MW; Chang, Soon-Heung, 1983 American Nuclear Society Mathematics and Computation Topical Meeting, American Nuclear Society, 1983 |
The Use of Burnup Credit in Criticality Control for the Korean Spent Fuel Management Program Koh, D.J; Jo, C.K; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Autumn Meeting, pp.245 - 250, 1997 |
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