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Showing results 53261 to 53280 of 276494

53261
Critical Factors in Protein Release from Biodegradable Polyester Microspheres

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

53262
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

53263
Critical Flux Enhancement with Coagulation in Crossflow Microfiltration

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

53264
Critical grain size for abnormal grain growth of BaTiO3 in air

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

53265
Critical Grain Size of Fine Aggregates in the View of the Rheology of Mortar

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

53266
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, Huen, JOURNAL OF THE AMERICAN CHEMICAL SOCIETY, v.128, no.48, pp.15360 - 15361, 2006-12

53267
Critical heat flux and flow pattern for water flow in annular geometry

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

53268
Critical heat flux and onset of nucleate boiling tests in a finned rod bundle

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

53269
Critical heat flux characteristic of magnetite-water nanofluid in pool boiling

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

53270
Critical Heat Flux during Flow Boiling Experiment with Surfactant Solutions

Sarwar, Mohammad Sohail; Jeong, Yong Hoon; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2007-05-11

53271
CRITICAL HEAT FLUX ENHANCEMENT

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

53272
Critical heat flux enhancement of nuclear fuel cladding with a nano-porous oxide film by anodization

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

53273
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

53274
Critical Heat Flux Enhancement: Nano-fluids and Others

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

53275
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 Hoon, Korean Nuclear Society Autumn Meeting, 2010-10-21

53276
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 Hoon, The 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8), 2010-10-12

53277
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 Hoon, The 7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7), 2010-11-17

53278
Critical heat flux experiments on the reactor vessel wall using 2-D slice test section

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

53279
Critical heat flux for downward flow boiling in a vertical narrow rectangular channel

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

53280
Critical heat flux for finned and unfinned geometries under low flow and low pressure conditions

Park, C; Chang, Soon-Heung; Baek, WP, NUCLEAR ENGINEERING AND DESIGN, v.183, no.3, pp.235 - 247, 1998-07

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