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Showing results 1 to 7 of 7

1
A heat transfer model development for CHF prediction with consideration of dry patch characteristics

Kam, Dong Hoon; Jeong, Yong Hoon; No, Hee Cheon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.148, 2020-02

2
Boric acid and boiling time effects on critical heat flux for corrosive and non-corrosive materials

Kam, Dong Hoon; Choi, Young Jae; Jeong, Yong Hoon, ANNALS OF NUCLEAR ENERGY, v.136, 2020-02

3
Experimental evaluations of the critical heat flux in terms of the heater dimensions, orientation, and surface morphology

Lee, Min Suk; Jung, Jun Yeong; Kam, Dong Hoon; Jeong, Yong Hoon, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.136, 2022-07

4
INFLUENCE OF FUEL-MATRIX INTERACTION ON THE BREAKAWAY SWELLING OF U-MO DISPERSION FUEL IN AL

Ryu, Ho Jin; Kim, Yeon Soo, NUCLEAR ENGINEERING AND TECHNOLOGY, v.46, no.2, pp.159 - 168, 2014-04

5
Metallurgical considerations for the fabrication of low-enriched uranium dispersion targets with a high density for Mo-99 production

Ryu, Ho Jin; Jung, Yong Jin; Nam, Ji Min; Park, Jong Man, JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, v.305, no.1, pp.31 - 39, 2015-07

6
Phase analyses of silicide or nitride coated U-Mo and U-Mo-Ti particle dispersion fuel after out-of-pile annealing

Kim, Woo Jeong; Palancher, Herve; Ryu, Ho Jin; Park, Jong Man; Nam, Ji Min; Bonnin, Anne; Honkimaeki, Veijo; et al, JOURNAL OF ALLOYS AND COMPOUNDS, v.589, pp.94 - 100, 2014-03

7
The modeling and simulation of the thermal conductivity of irradiated U-Mo dispersion fuel: Estimation of the thermal conductivity of the interaction layer

Mistarihi, Qusai M.; Hwang, Jun Teak; Ryu, Ho Jin, JOURNAL OF NUCLEAR MATERIALS, v.510, pp.199 - 209, 2018-11

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