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Dive into the research topics where Joo Hwan Park is active.

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Featured researches published by Joo Hwan Park.


Journal of Nuclear Science and Technology | 2007

Application of a Zircaloy/Steam Oxidation Model to a CFD Code and its Validation against a CANDU Fuel Channel Experiment : CS28-2

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

Development of a CFD model for the CANDU-6 moderator analysis using a coupled solver

Churl Yoon; Joo Hwan Park


Annals of Nuclear Energy | 2011

The effect of a CANDU fuel bundle geometry variation on thermalhydraulic performance

Jun Ho Bae; Joo Hwan Park


Annals of Nuclear Energy | 2011

Analytical prediction of turbulent friction factor for a rod bundle

Jun Ho Bae; Joo Hwan Park


Annals of Nuclear Energy | 2008

Irradiation tests and post-irradiation examinations of DUPIC fuel

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

A blind simulation of RD-14M small-break LOCA experiments using CATHENA code

Hyoung Tae Kim; Bo Wook Rhee; Joo Hwan Park


Annals of Nuclear Energy | 2009

Development and validation of a CATHENA fuel channel model for a post-blowdown analysis of the high temperature thermal–chemical experiment CS28-1

Bo Wook Rhee; Hyoung Tae Kim; Joo Hwan Park


Nuclear Engineering and Design | 2008

CFX simulation of a horizontal heater rods test

Hyoung Tae Kim; Bo Wook Rhee; Joo Hwan Park


Annals of Nuclear Energy | 2006

Application of the finite volume method to the radial conduction model of the CATHENA code

Hyoung Tae Kim; Bo Wook Rhee; Joo Hwan Park


Annals of Nuclear Energy | 2014

The effect of inner ring modification of standard 37-element fuel on CHF enhancement

Joo Hwan Park; Yong Mann Song

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