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

Showing results 1781 to 1800 of 10271

1781
Assessment of APR-1400 emergency core cooling system performance for design basis LOCA redefinition

Kang, Dong Gu; Ahn, Seung-Hoon; Chang, Soon Heung; Huh, Byung-Gil; Bang, Young-Seok; Seul, Kwang-Won, 2014 22nd International Conference on Nuclear Engineering, ICONE 2014, American Society of Mechanical Engineers (ASME), 2014-07

1782
Assessment of Beam Dump Activation for RAON Heavy Ion Accelerator in KOREA

Cho, Gyuseong; Lee, E; Lee, C; Yang, S; Lee, Y; Park, K, International Radiation Protection Association, International Radiation Protection Association, 2016-05-11

1783
Assessment of CHF correlations for internally heated concentric annulus channels

Park, JW; Baek, WP; Chang, Soon-Heung, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.23, no.8, pp.1077 - 1086, 1996-12

1784
Assessment of concentration limit for the safe disposal of very low leve wastes = 극저준위 폐기물의 안전한 처분을 위한 농도 제한치에 대한 연구link

Nam, Yun-seog; 남윤석; et al, 한국과학기술원, 2008

1785
Assessment of critical heat flux (chf) performance in water using sic-coated plate and -sic pipe under atmospheric pressure

Kam, Dong Hoon; Lee, Jong Hyuk; Lee, Tae-Seung; Jeong, Yong Hoon, 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.1693 - 1700, Korean Nuclear Society, 2013-04-18

1786
Assessment of dead layer in HPGe detector for in-situ gamma spectroscopy

김준하; 조규성; 홍상범; 서범경, 2020 한국원자력학회 춘계학술대회, 한국원자력학회, 2020-07-09

1787
Assessment of Dryout Heat Flux Correlations for Particle Beds

Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1997-05-01

1788
Assessment of Energy Security, Environment and Health Risks by Energy Sources for Energy Policy of Korea

Kim, HyoIm; Yim, Man-Sung, The 6th International Conference on Nuclear and Renewable Energy Resources (NURER2018), Korea Advanced Institute of Science and Technology (KAIST), 2018-10-02

1789
Assessment of Feasibility of On-Line Monitoring Systems for Nuclear Power Plants in Korea

LEE, Seung Min; Seong, Poong-Hyun, ICI 2011 (ISOFIC + CSEPC +ISSNP), 2011-08-23

1790
Assessment of fuel cycle proliferation resistance dynamics using coupled isotopic characterization

Skutnik, Steven E.; Yim, Man-Sung, NUCLEAR ENGINEERING AND DESIGN, v.241, no.8, pp.3270 - 3282, 2011-08

1791
Assessment of geometric uncertainties in gated stereotactic ablative body radiotherapy(SABR)

Chung, H; Cho, B; Cho, Seungryong, The 7th Korea-Japan Joint Meeting on Medical Physics, KJMP, 2014-09-26

1792
Assessment of High Chromium Oxide Dispersion Strengthened Steels for Nuclear Applications

Jang, Changheui; Kim, In Sup; Lee, J.S.; Kimura, A., EUROMAT 2005, 2005-09-20

1793
Assessment of HTGR helium compressor analysis tool based on Newton-Raphson numerical application to throughflow analysis

Kim, J.H.; Kim, H.M.; No, Hee Cheon, Fourteenth International Conference on Nuclear Engineering 2006, ICONE 14, 2006-07-17

1794
Assessment of Nominal Ionosphere Spatial Decorrelation for LAAS

Lee, Ji Hyun; Pullen, Sam; Datta-Barua, Seebany; Enge, Per, 2006 IEEE/ION Position, Location, And Navigation Symposium, 2010-11

1795
Assessment of passive containment cooling concepts for advanced pressurized water reactors

Lee, SW; Baek, WP; Chang, Soon-Heung, ANNALS OF NUCLEAR ENERGY, v.24, no.6, pp.467 - 475, 1997-04

1796
Assessment of pool boiling CHF enhancement using magnetite and alumina water nanofluids at higher pressure

Lee, Jong Hyuk; Lee, Taeseung; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, KNS, 2012-10

1797
Assessment of Potential Radiation Exposures by Uncontrolled Recycle or Reuse of Radioactive Scrap Metals

sang-yoon lee; Lee, Kun Jai, WASTE MANAGEMENT, v.19, no.7-8, pp.483 - 493, 1999

1798
Assessment of Proliferation Resistance of Nuclear Reactor Systems Using Fuzzy Logic Based Barrier Method

Jun Li; Yim Man-Sung; David N. McNelis, INMM (Institute of Nuclear Materials Management) 46th Annual Meeting, INMM (Institute of Nuclear Materials Management) 46th Annual Meeting, 2005-07

1799
Assessment of proliferation resistance of nuclear reactors using fuzzy logic based barrier method

Li Jun; Yim Man-Sung; McNelis, David N., 2005 Annual Meeting - American Nuclear Society, v.92, no.2005, pp.276 - 277, Transactions of the American Nuclear Society, 2005-06

1800
Assessment of Proliferation Resistance of Nuclear Reactors Using Fuzzy Logic Based Barrier Method

Jun Li; Yim Man-Sung; David N. McNelis, Transactions of the American Nuclear Society, v.92, no.2005, pp.276 - 277, American Nuclear Society, 2005-06

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