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Showing results 44221 to 44240 of 278095

44221
CHF enhancement of SiC nanofluid in pool boiling experiment

Song, Sub Lee; Lee, Ju Hyung; Chang, Soon-Heung, EXPERIMENTAL THERMAL AND FLUID SCIENCE, v.52, pp.12 - 18, 2014-01

44222
CHF Enhancement of SiC-water Nanofluids in Pool Boiling Experiment

Song, Sub Lee; Lee, Ju Hyung; Chang, Soon-Heung, 2012 PBNC Proceddings of th 18th Pacific Basin Nuclear Conference, Pacific Nuclear Council, 2012-03-20

44223
CHF Enhancement under Pool Boiling Using Nanofluids

Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2008-05-29

44224
CHF Experiment and CFD Analysis in 2*2 Rod Bundle with Swirl-Type Mixing Vane

Shin, BS; Chang, Soon-Heung, 한국원자력학회 학술발표대회, 한국원자력학회, 2005-05

44225
CHF experiment and CFD analysis in a 2 x 3 rod bundle with mixing vane

Shin, Byung Soo; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.239, no.5, pp.899 - 912, 2009-05

44226
CHF Experiment for Heater Inclination Angle and Material Effect for Downward Facing Surface

Jung, Jun Yeong; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2017-05-18

44227
CHF experiment with downward-facing carbon and stainless steel plates under pressurized conditions

Kam, Dong Hoon; Choi, Young Jae; Jeong, Yong Hoon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.125, pp.670 - 680, 2018-10

44228
CHF Experiments for IVR-EVC using 2-D Slice Test Section

Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2002-05-23

44229
CHF Experiments of SUS304 Heater at 30 and 60 Degree Inclination Angles with Downward Facing Geometry for IVR-ERVC

정준영; 감동훈; 정용훈, 2019 한국원자력학회 추계학술발표회, 한국원자력학회, 2019-10-24

44230
CHF Experiments on the Reactor Vessel Wall using 2-D Slice Test Section

Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2003-10-05

44231
CHF Experiments under Realistic Severe Accident Condition for IVR-ERVC Strategy

Kim, TI; Park, HM; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2010-10-21

44232
CHF EXPERIMENTS UNDER REALISTIC SEVERE ACCIDENT CONDITION FOR IVR-ERVC STRATEGY

Kim, Tae Il; Chang, Soon-Heung, 2012 PBNC Proceddings of th 18th Pacific Basin Nuclear Conference, Pacific Nuclear Council, 2012-03-21

44233
CHF experiments using a 2-D curved test section with additives for IVR-ERVC strategy

Kim, Tae-Il; Park, Hae-Min; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.243, pp.272 - 278, 2012-02

44234
CHF Experiments using a 2-D Curved Test Section with Additives for IVR-ERVC Strategy

Kim, TI; Park, HM; Chang, Soon-Heung, 2011 NURETH14, NURETH-14, 2011-09-25

44235
CHF experiments with a plate-type large size of carbon steel heater considering long-term oxidation process

이민석; 정준영; 감동훈; 정용훈, 2021 한국원자력학회 추계학술발표회, 한국원자력학회, 2021-10-21

44236
CHF Experiments with Micron-sized Amorphous and Porous Particles on Plate-shaped Heater for Development of Multi-functional Magnetic Nanoparticles

이민석; 감동훈; 정용훈, 2019 한국원자력학회 추계학술발표회, 한국원자력학회, 2019-10-25

44237
CHF for Downward-facing Flat Plates Considering Pressure Up to 2 Bar Condition, Width and Material Effects

KAM, Dong Hoon; Choi, Young Jae; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2016-05-13

44238
CHF Measurement for Downward Facing SUS 304 and Carbon Steel Plates under Atmospheric and Pool Boiling Conditions

KAM, DONG HOON; Park, Hae Min; Choi, Young Jae; Jeong, Yong Hoon, The 16th International Topical Meeting on Nuclear Reactor Thermalhydraulics(NURETH-16), American Nuclear Society, 2015-09-01

44239
CHF Measurement for Downward-Facing Stainless Steel and Carbon Steel Flat Plates under Pool Boiling Condition

Kam, Dong Hoon; Choi, Young Jae; Jeong, Yong Hoon, 2016 International Congress on Advances in Nuclear Power Plants, ICAPP 2016, pp.2054 - 2060, American Nuclear Society, 2016-04-20

44240
CHF Measurement for Flat Plates Considering Dimensional Effects (Length & Width) under Atmospheric and Pool Boiling Conditions

KAM, DONG HOON; Choi, Young Jae; Jeong, Yong Hoon; Park, Hae Min, The 11th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-11), Korean Nuclear Society and American Nuclear Society, 2016-10-10

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