Browse by Title

Showing results 45661 to 45680 of 232144

45661
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

45662
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

45663
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

45664
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

45665
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

45666
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

45667
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

45668
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

45669
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

45670
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

45671
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

45672
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

45673
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

45674
Critical heat flux for finned and unfinned geometries under low flow and low pressure conditions

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

45675
Critical Heat flux for Natural-Circulation of Water Under Low Pressure

Kim, YI; Chang, Soon-Heungresearcher, The 2nd International Conference on Multiphase Flow, pp.1 - 6, 1995

45676
Critical heat flux for SiC- and Cr-coated plates under atmospheric condition

Kam, Dong Hoon; Lee, Jong Hyuk; Lee, Tae-Seung; Jeong, Yong Hoonresearcher, ANNALS OF NUCLEAR ENERGY, v.76, pp.335 - 342, 2015-02

45677
Critical Heat Flux Measurement for downward facing flat plates (SUS 304, SA 508) under atmospheric and pool boiling conditions

Kam, Dong Hoon; Park, Hae Min; Choi, Young Jae; Jeong, Yong Hoonresearcher, The Seventh China-Korea Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-7), Nuclear Power Institute of China, Korea Atomic Energy Research Institute, 2015-10-15

45678
Critical Heat Flux Measurement of SiC- and Cr-coated Plates, Bare Stainless Steel Plate and Zircaloy-4 Plate Under Atmospheric and Pool Boiling Conditions

Kam, Dong Hoon; Lee, Jong Hyuk; Lee, Taeseung; Jeong, Yong Hoonresearcher, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29

45679
Critical Heat Flux Measurement of SiC- and Cr-coated surfaces with reference surfaces for pool boiling and α-SiC tube for flow boiling under atmospheric conditions, Surface change of SiC-coated surface

Kam, Dong Hoon; Jeong, Yong Hoonresearcher, International Workshop on Nuclear Safety and Severe Accident, The International Atomic Energy Agency, 2014-09-03

45680
Critical heat flux model on a downward facing surface for application to the IVR conditions

Park, Hae Min; Jeong, Yong Hoonresearcher; Carnevali, Sofia, NUCLEAR ENGINEERING AND DESIGN, v.330, pp.317 - 324, 2018-04

Discover

Type

. next

Open Access

Date issued

. next

Subject

. next

rss_1.0 rss_2.0 atom_1.0