Showing results 1 to 14 of 14
A Study on the Correlations Development for Film boiling Heat Transfer on Spheres Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1998-05-01 |
A Study on the Non-Heating CHF Experiments Using Drilled Plates Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1999-05-28 |
A Study on the Non-Heating Simulation ofPool Boiling CHF on Flat Plates Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2000-10-26 |
(A) numerical and experimental investigation of the single-phase natural circulation system with multiloop = 다회로의 단상 자연 순환계에 관한 실험및 수치해석적 연구link Baek, Won-Pil; 백원필; et al, 한국과학기술원, 1984 |
(A) study of critical heat flux at low pressure and low velocity conditions = 저압, 저유속 조건에서의 임계 열유속에 관한 연구link Baek, Won-Pil; 백원필; et al, 한국과학기술원, 1991 |
An Experimental Study of the Pool-Boiling CHF on Downward-Facing Plates Yang, Soo-Hyung; Baek, Won-Pil; Chang, Soon-Heung, NUCLEAR ENGINEERING AND TECHNOLOGY , v.26, no.4, pp.493 - 501, 1994-04 |
Assessment of Dryout Heat Flux Correlations for Particle Beds Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1997-05-01 |
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 |
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 |
Coolant Options and Critical Heat Flux Issues in Fusion Reactor Divertor Design Baek, Won-Pil; Chang, Soon Heung, NUCLEAR ENGINEERING AND TECHNOLOGY , v.29, no.4, pp.348 - 359, 1997-08 |
Experimental and Analytical Study on the Simulation of Pool Boiling CHF Based on Macrolayer Dryout Model Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2001-05-24 |
Mass Flux and Gap Effects on the CHF Experiments for IVR-EVC using 2-D Slice Test Section Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, Third Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, 2002-10-13 |
Non-Heating Simulation of Pool-Boiling Critical Heat Flux Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, American Nuclear Society 2002 Annual Meeting, American Nuclear Society, 2002-06-09 |
Proposed Concept of a Tube-Type Passive Water-Cooled Reactor Without Emergency Core Cooling System Chang, Soon Heung; Baek, Won-Pil; Lee, Goung-Jin; Lee, Jae-Young, NUCLEAR ENGINEERING AND TECHNOLOGY , v.26, no.2, pp.161 - 167, 1994 |
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