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

Showing results 2241 to 2260 of 8497

2241
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

2242
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

2243
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

2244
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

2245
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

2246
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

2247
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

2248
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

2249
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

2250
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

2251
Critical Heat Flux of Water in Vertical Round Tube at Low Pressure and Low Flow Conditions

Kim, HC; Baek, WP; Chang, Soon-Heungresearcher, The 1st Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, 1998

2252
Critical heat flux of water in vertical round tubes at low pressure and low flow conditions

Kim, HC; Baek, WP; Chang, Soon-Heungresearcher, NUCLEAR ENGINEERING AND DESIGN, v.199, no.1-2, pp.49 - 73, 2000-06

2253
Critical Heat Flux of Water in Vertical Round Tubes at Low-Pressure and Low-Flow Conditions

Park, JW; Kim, HC; Baek, WP; Chang, Soon-Heungresearcher, The 8th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, 1997

2254
Critical heat flux on downward-facing carbon steel flat plates under atmospheric condition

Kam, Dong Hoon; Choi, Young Jae; Jeong, Yong Hoonresearcher, EXPERIMENTAL THERMAL AND FLUID SCIENCE, v.90, pp.22 - 27, 2018-01

2255
Critical heat flux performance for flow boiling of R-134a in vertical uniformly heated smooth tube and rifled tubes

Kim, CH; Bang, IC; Chang, Soon-Heungresearcher, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.48, no.14, pp.2868 - 2877, 2005-07

2256
Critical heat flux prediction using genetic programming for water flow in vertical round tubes

Lee, DG; Kim, HG; Baek, WP; Chang, Soon-Heungresearcher, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.24, no.7, pp.919 - 929, 1997

2257
Critical heat flux under flow oscillation of a water at low-pressure, low-flow conditions

Kim, YI; Baek, WP; Chang, Soon-Heungresearcher, NUCLEAR ENGINEERING AND DESIGN, v.193, no.1-2, pp.131 - 143, 1999-09

2258
Critical heat flux under flow oscillations and natural circulation conditions = 유동진동과 자연순환 조건에서의 임계 열유속link

Kim, Yun-Il; 김윤일; et al, 한국과학기술원, 1997

2259
Critical Pressure Ratio and Critical Flow Rate in a Safety Valve

No, Hee Cheonresearcher; Kim, Se Won, 한국원자력학회 추계발표회, 한국원자력학회, 1999

2260
Critical two-phase flow of initially subcooled and saturated water = 과냉각수및 포화수에 대한 임계 이상 유량에 관한 연구link

Son, Se-Do; 손세도; et al, 한국과학기술원, 1986

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