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Results 21-30 of 31 (Search time: 0.005 seconds).

NO Title, Author(s) (Publication Title, Volume Issue, Page, Issue Date)
21
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

22
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

23
Korea looks beyond the next generation

Chang, Soon-Heungresearcher; No, Hee Cheonresearcher; Baek, WP; Lee, SI; Lee, SW, NUCLEAR ENGINEERING INTERNATIONAL, v.42, no.511, pp.12 - 12, 1997-02

24
Visualization of the subcooled flow boiling of R-134a in a vertical rectangular channel with an electrically heated wall

Bang, IC; Chang, Soon-Heungresearcher; Baek, WP, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.47, no.19-20, pp.4349 - 4363, 2004-09

25
Visualization of a principle mechanism of critical heat flux in pool boiling

Bang, IC; Chang, Soon-Heungresearcher; Baek, WP, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.48, no.25-26, pp.5371 - 5385, 2005-12

26
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

27
Non-heating simulation of pool-boiling critical heat flux

Jeong, Yong Hoonresearcher; Baek, WP; Chang, Soon-Heungresearcher, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.45, no.19, pp.3987 - 3996, 2002-09

28
An integral equation model for critical heat flux at subcooled and low quality flow boiling

Chun, TH; Baek, WP; Chang, Soon-Heungresearcher, NUCLEAR ENGINEERING AND DESIGN, v.199, no.1-2, pp.13 - 29, 2000-06

29
A STUDY OF CRITICAL HEAT-FLUX FOR LOW FLOW OF WATER IN VERTICAL ROUND TUBES UNDER LOW-PRESSURE

Chang, Soon-Heungresearcher; Baek, WP; Bae, TM, NUCLEAR ENGINEERING AND DESIGN, v.132, no.2, pp.225 - 237, 1991-12

30
Nuclear Reactor Thermal Hydraulics (NURETH-10) special issue - Part 2 - Foreword

Chang, Soon-Heungresearcher; Baek, WP; Rempe, J, NUCLEAR TECHNOLOGY, v.152, no.2, pp.143 - 143, 2005-11

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