Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Type Conference

Showing results 4761 to 4780 of 5608

4761
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

4762
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

4763
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

4764
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

4765
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

4766
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

4767
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

4768
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

4769
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

4770
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

4771
The Statistical Analysis for the Characteristics of Low-Level Wastes Generated from PWR

Lee, Kun Jai, Waste Management '91, pp.329 - 335, 1991

4772
The Statistical Analysis for the Characteristics of Low-Level Wastes Generated from PWR

이건재, 한국원자력학회 학술발표회 ( 춘계 ), pp.505 - 524, 1991

4773
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

4774
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

4775
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

4776
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

4777
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

4778
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

4779
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

4780
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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