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Publication
Featured researches published by Joo Hwan Park.
Journal of Nuclear Science and Technology | 2007
Hyoung Tae Kim; Bo Wook Rhee; Joo Hwan Park
Oxidation of a Zircaloy cladding exposed to high-temperature steam is an important phenomenon in the safety analysis of CANDU reactors during a postulated loss-of-coolant accident (LOCA), since a Zircaloy/steam reaction is highly exothermic and results in hydrogen production. As part of a computational fluid dynamics (CFD) simulation of the CS28-2 high-temperature experiment for this accident analysis, two Zircaloy/steam reaction models based on a parabolic rate law are implemented in a commercial CFD code (CFX-10) through a user FORTRAN. It is confirmed that the present oxidation models for the CFX-10 reproduce the results of each empirical correlation in the verification tests well. Then the CFX-10 predictions of a temperature rise and hydrogen production due to Zircaloy/steam oxidation are compared with the results of the CS28-2 experiment. From these validation processes, it is shown that the Urbanic-Heidrick model, which is widely used in CANDU fuel channel codes, is also applicable to a CFX-10 simulation of Zircaloy/steam oxidation in a CANDU fuel channel.
Annals of Nuclear Energy | 2008
Churl Yoon; Joo Hwan Park
Annals of Nuclear Energy | 2011
Jun Ho Bae; Joo Hwan Park
Annals of Nuclear Energy | 2011
Jun Ho Bae; Joo Hwan Park
Annals of Nuclear Energy | 2008
Chang Je Park; Kweon Ho Kang; Ho Jin Ryu; Cheol Yong Lee; In Ha Jung; Je Sun Moon; Joo Hwan Park; Sang Ho Na; Kee Chan Song
Annals of Nuclear Energy | 2011
Hyoung Tae Kim; Bo Wook Rhee; Joo Hwan Park
Annals of Nuclear Energy | 2009
Bo Wook Rhee; Hyoung Tae Kim; Joo Hwan Park
Nuclear Engineering and Design | 2008
Hyoung Tae Kim; Bo Wook Rhee; Joo Hwan Park
Annals of Nuclear Energy | 2006
Hyoung Tae Kim; Bo Wook Rhee; Joo Hwan Park
Annals of Nuclear Energy | 2014
Joo Hwan Park; Yong Mann Song