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

Showing results 1 to 6 of 6

1
A zero-dimensional dryout heat flux model based on mechanistic interfacial friction models for two-phase flow regimes with channel flow in a packed bed

Yeo, DY; No, Hee-Cheon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.141, pp.554 - 568, 2019-10

2
An assessment methodology for in-vessel corium retention by external reactor vessel cooling during severe accidents in PWRs

Park, Jae Hong; Jeong, Yong Hoon; Baek, Won Pil; Chang, Soon Heung, ANNALS OF NUCLEAR ENERGY, v.28, no.12, pp.1237 - 1250, 2001-08

3
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

4
Combined effect of a corrodible material and acidic fluid on flow boiling crisis

Jung, Jun Yeong; Lee, Min Suk; Jeong, Yong Hoon, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.143, 2023-04

5
Critical heat flux experiments on the reactor vessel wall using 2-D slice test section

Jeong, Yong Hoon; Chang, Soon-Heung; Baek, WP, NUCLEAR TECHNOLOGY, v.152, no.2, pp.162 - 169, 2005-11

6
Flow boiling experiments for CHF evaluation under downward-facing heating including flow visualization: Effects of pressure, orientation, mass flux, and local quality

Jung, Jun Yeong; Lee, Min Suk; Park, Hae Min; Jeong, Yong Hoon, ANNALS OF NUCLEAR ENERGY, v.171, 2022-06

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