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Featured researches published by Chul-Hwa Song.


Nuclear Engineering and Technology | 2014

RECENT IMPROVEMENTS IN THE CUPID CODE FOR A MULTI-DIMENSIONAL TWO-PHASE FLOW ANALYSIS OF NUCLEAR REACTOR COMPONENTS

Han Young Yoon; Jae Ryong Lee; Hyungrae Kim; Ik Kyu Park; Chul-Hwa Song; Hyoung Kyu Cho; Jae Jun Jeong

The CUPID code has been developed at KAERI for a transient, three-dimensional analysis of a two-phase flow in light water nuclear reactor components. It can provide both a component-scale and a CFD-scale simulation by using a porous media or an open media model for a two-phase flow. In this paper, recent advances in the CUPID code are presented in three sections. First, the domain decomposition parallel method implemented in the CUPID code is described with the parallel efficiency test for multiple processors. Then, the coupling of CUPID-MARS via heat structure is introduced, where CUPID has been coupled with a system-scale thermal-hydraulics code, MARS, through the heat structure. The coupled code has been applied to a multi-scale thermal-hydraulic analysis of a pool mixing test. Finally, CUPID-SG is developed for analyzing two-phase flows in PWR steam generators. Physical models and validation results of CUPID-SG are discussed.


Nuclear Engineering and Design | 2003

Effect of the yaw injection angle on the ECC bypass in comparison with the horizontal DVI

T.S. Kwon; Chul-Hwa Song; Byong-Jo Yun; Hyoung Kyu Cho

Abstract The comparison tests for the direct emergency core cooling (ECC) bypass fraction were experimentally performed with a typical direct vessel injection (DVI) nozzle and an ECC column nozzle having a yaw injection angle to the gravity axis. The ECC yaw injection nozzle is newly introduced to make an ECC water column in the downcomer region. The yaw injection angle of the ECC water relative to the gravity axis is varied from 0 to (±)90° stepped by 45°. The tests are performed in the air–water separate effect test facility (direct injection visualization and analysis (DIVA)), which is a 1/7.07 linearly scaled-down model of the APR1400 nuclear reactor. The test results show that (1) if the ECC water column is injected into the wake region which is induced by the hot leg blunt body in the downcomer annulus, the ECC bypass fraction is greatly reduced compared with the typical horizontal ECC injection which makes ECC film on the downcomer wall. At the same time, the ECC penetration toward the lower downcomer region becomes larger than those of a typical horizontal type of direct vessel injection on the downcomer wall vertically. (2) If the ECC water column is injected near the broken cold leg, the ECC water is directly bypassed. Thus, the ECC penetration fraction is greatly reduced compared with a typical film type of the horizontal ECC injection. (3) In order to minimize the ECC bypass fraction, the ECC water should be injected toward the wake region of the hot leg blunt bodies.


Nuclear Engineering and Design | 2004

Scaling for the ECC bypass phenomena during the LBLOCA reflood phase

Byong-Jo Yun; Hyoung Kyu Cho; Dong-Jin Euh; Chul-Hwa Song; Goon-Cherl Park


Nuclear Engineering and Design | 2010

Characteristics of the local bubble parameters of a subcooled boiling flow in an annulus

Byong-Jo Yun; Byoung-Uhn Bae; Dong-Jin Euh; Goon-Cherl Park; Chul-Hwa Song


Nuclear Engineering and Design | 2008

Downcomer boiling phenomena during the reflood phase of a large-break LOCA for the APR1400

Byong-Jo Yun; Dong-Jin Euh; Chul-Hwa Song


Nuclear Engineering and Design | 2005

Experimental validation of the modified linear scaling methodology for scaling ECC bypass phenomena in DVI downcomer

Hyoung Kyu Cho; Byong-Jo Yun; Chul-Hwa Song; Goon-Cherl Park


Nuclear Engineering and Design | 2004

Numerical simulation of an improved five-sensor probe method for local interfacial area concentration measurement

Dong-Jin Euh; Byong-Jo Yun; Chul-Hwa Song


Nuclear Engineering and Technology | 2015

Quantitative observation of co-current stratified two-phase flow in a horizontal rectangular channel

Seungtae Lee; Dong-Jin Euh; Seok Kim; Chul-Hwa Song


Nuclear Engineering and Design | 2018

Extended validation of a developing post-dryout heat transfer correlation over a wide range of pressure conditions

Ngoc Hung Nguyen; Sang-Ki Moon; Chul-Hwa Song


Nuclear Engineering and Design | 2017

Improvements of COBRA-TF on the effect of flow blockage during a LB LOCA with consideration of fuel relocation phenomenon

Ngoc Hung Nguyen; Jongrok Kim; SeungHyun Hong; Sang-Ki Moon; Chul-Hwa Song

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Byong-Jo Yun

Pusan National University

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Hyoung Kyu Cho

Seoul National University

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Goon-Cherl Park

Seoul National University

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Ngoc Hung Nguyen

Korea University of Science and Technology

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Byoung-Uhn Bae

Seoul National University

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