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1
An experimental study of thermal-hydraulic phenomena in the downcomer with a direct vessel injection system of APR1400 during the LBLOCA reflood phase

Lee, DW; No, Hee Cheon; Kim, HG; Oh, SJ, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.41, no.4, pp.440 - 447, 2004-04

2
Critical heat flux prediction using genetic programming for water flow in vertical round tubes

Lee, DG; Kim, HG; Baek, WP; Chang, Soon-Heung, INTERNATIONAL COMMUNICATIONS IN HEAT AND MASS TRANSFER, v.24, no.7, pp.919 - 929, 1997

3
Development of an advanced human-machine interface for next generation nuclear power plants

Chang, Soon-Heung; Choi, SS; Park, JK; Heo, GY; Kim, HG, RELIABILITY ENGINEERING SYSTEM SAFETY, v.64, no.1, pp.109 - 126, 1999-04

4
Development strategies of an intelligent human-machine interface for next generation nuclear power plants

Choi, SS; Park, JK; Hong, JH; Kim, HG; Chang, Soon-Heung; Kang, KS, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.43, no.3, pp.2114 - 3, 1996-06

5
Effect of tellurium on the microstructure and mechanical properties of Fe-14Cr oxide-dispersion-strengthened steels produced by additive manufacturing

Arkhurst, BM; Bae, JH; Na, MY; Chang, HJ; Kim, HG; Kim, IH; Ryu, Ho Jin; et al, JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, v.95, pp.114 - 126, 2021-12

6
Identification of reactor vessel failures using spatiotemporal neural networks

Roh, CH; Chang, HS; Kim, HG; Chang, Soon-Heung, IEEE TRANSACTIONS ON NUCLEAR SCIENCE, v.43, no.6, pp.3229 - 2, 1996-12

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