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Results 21-30 of 252 (Search time: 0.011 seconds).

NO Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date)
21
Critical Heat flux for Natural-Circulation of Water Under Low Pressure

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

22
A Severe Accident Management Supporting system Using Quantified Containment Event Trees

Chang, HS; Chang, Soon-Heung, International Conference on Probabilistic Safety Assessment Methodology and Applications, 1995

23
Development of a Reactor Vessel Failure Diagnosis System for Accident Management

No, CH; Chang, Soon-Heung, International Conference on Probabilistic Safety Assessment Methodology and Applications, 1995

24
Thermal Performance Test through On-line Turbine Cycle Performance Monitoring in Nuclear Power Plants

Heo, GY; Lee, SJ; Choi, SS; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 1999

25
Natural Circulation of the Encapsulated Nuclear Heat Source

Lee, KG; Chang, Soon-Heung, 2000 ANS Winter Meeting, ANS, 2000

26
The Effect of Vibration on Critical Heat Flux in a Vertical Round Tube

Lee, Y.H.; Chang, Soon-Heung, The 3rd Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, v.40, no.10, pp.734 - 743, 2002

27
Algebraic Model for Root-Cause Diagnosis in Nuclear Turbine Cycles

Heo, GY; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2004

28
Development of a Heated Length-to-Diameter Correction Factor for Critical Heat Flux Prediction

Lee, YH; Baek, WP; Chang, Soon-Heung, The 1st Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, 1998

29
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

30
Development of Performance Meassure for Advanced Alarm System Using Signal Detection Theory

Park, JK; Choi, SS; Chang, Soon-Heung, '96 CSEPC, 1996

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