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Showing results 45641 to 45660 of 232039

45641
Critical factors in protein release from biodegradable poly(lactide-co-glycolide) microspheres

Tae Gwan Park, 한국고분자학회 추계 학술발표회, pp.148 - 149, 1996-10-01

45642
Critical Factors in Protein Release from Biodegradable Polyester Microspheres

Tae Gwan Parkresearcher, The 213th American Chemical Society, Division of Biochemical Technology, pp.0 - 0, 1997-03-01

45643
Critical Flow Rates of Subcooled Water Through Short Pipes with Small Diameters

Chun, Moon Hyun, Proc. of the 8th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), pp.759 - 766, 1997

45644
Critical Flux Enhancement with Coagulation in Crossflow Microfiltration

Park, Heekyungresearcher, 1st World Water Congress of the International Water Association (IWA), 2000-07

45645
Critical grain size for abnormal grain growth of BaTiO3 in air

Yang, Dong-Yeol; Choi, Si-Young; Kang, Suk-Joong Lresearcher, JOURNAL OF THE CERAMIC SOCIETY OF JAPAN, v.114, pp.970 - 973, 2006-11

45646
Critical Grain Size of Fine Aggregates in the View of the Rheology of Mortar

Han, Dongyeop; Kim, Jae Hongresearcher; Lee, Jinhyun; Kang, Su-Tae, INTERNATIONAL JOURNAL OF CONCRETE STRUCTURES AND MATERIALS, v.11, no.4, pp.627 - 635, 2017-12

45647
Critical guest concentration and complete tuning pattern appearing in the binary clathrate hydrates

Kim, Do-Youn; Park, Jeasung; Lee, Jong-won; Ripmeester, John A.; Lee, Huenresearcher, JOURNAL OF THE AMERICAN CHEMICAL SOCIETY, v.128, no.48, pp.15360 - 15361, 2006-12

45648
Critical heat flux and flow pattern for water flow in annular geometry

Park, JW; Baek, WP; Chang, Soon-Heungresearcher, NUCLEAR ENGINEERING AND DESIGN, v.172, no.1-2, pp.137 - 155, 1997

45649
Critical heat flux and onset of nucleate boiling tests in a finned rod bundle

Chae, HT; Park, JH; Kim, H; Chang, Soon-Heungresearcher, NUCLEAR TECHNOLOGY, v.148, no.3, pp.287 - 293, 2004-12

45650
Critical heat flux characteristic of magnetite-water nanofluid in pool boiling

Lee, Jong Hyuk; Lee, Taeseung; Jeong, Yong Hoonresearcher, The 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8), Thermal Hydraulics Divisions of AESJ, KNS, 2012-12

45651
Critical Heat Flux during Flow Boiling Experiment with Surfactant Solutions

Sarwar, Mohammad Sohail; Jeong, Yong Hoonresearcher; Chang, Soon-Heungresearcher, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2007-05-11

45652
CRITICAL HEAT FLUX ENHANCEMENT

Chang, Soon-Heungresearcher; Jeong, Yong Hoonresearcher; Shin, Byung-Soo, NUCLEAR ENGINEERING AND TECHNOLOGY, v.38, no.8, pp.753 - 762, 2006-11

45653
Critical heat flux enhancement of nuclear fuel cladding with a nano-porous oxide film by anodization

유형석; 정용훈researcher, 2018 한국원자력학회 춘계학술발표회, 한국원자력학회, 2018-05-18

45654
Critical heat flux enhancement of nuclear fuel cladding with nano-porous oxide film by surface anodization = 표면 양극산화법으로 제조된 나노 다공성 산화막을 가진 핵연료 피복관의 임계열유속 증진link

Yu, Hyoung Suk; Jeong, Yong Hoon; et al, 한국과학기술원, 2018

45655
Critical Heat Flux Enhancement: Nano-fluids and Others

Chang, Soon-Heungresearcher; Jeong, Yong Hoonresearcher, International Workshop on New Horizons in Nuclear Reactor Thermal Hydraulics, 2008-01-07

45656
Critical Heat Flux Experiments for In-Vessel Retention External Reactor Vessel Cooling Strategy using 2-D Slice Test Section

Park, Hae Min; Kim, Taeil; Heo, Sun; Jeong, Yong Hoonresearcher, Korean Nuclear Society Autumn Meeting, 2010-10-21

45657
Critical Heat Flux Experiments for In-Vessel Retention External Reactor Vessel Cooling Strategy using 2-D Slice Test Section

Park, Hae Min; Kim, Taeil; Heo, Sun; Jeong, Yong Hoonresearcher, The 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8), 2010-10-12

45658
Critical Heat Flux Experiments for In-Vessel Retention External Reactor Vessel Cooling Strategy Using 2-D Slice Test Section

Park, Hae Min; Kim, Taeil; Heo, Sun; Jeong, Yong Hoonresearcher, The 7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7), 2010-11-17

45659
Critical heat flux experiments on the reactor vessel wall using 2-D slice test section

Jeong, Yong Hoonresearcher; Chang, Soon-Heungresearcher; Baek, WP, NUCLEAR TECHNOLOGY, v.152, no.2, pp.162 - 169, 2005-11

45660
Critical heat flux for downward flow boiling in a vertical narrow rectangular channel

Lee, Juhyung; Daesung Jo; Heetaek Chae; Chang, Soon-Heungresearcher, 2013 ANS Winter Meeting and Technology Expo, American Nuclear Society, 2013-11-11

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