Numerical and analytical predictions of nuclear steam generator secondary side flow field during blowdown due to a feedwater line break

by Jong Chull Jo, Jae-Jun Jeong, Frederick J. Moody
Published 2021-03-01

Measurement of local wall temperature and heat flux using the two-thermocouple method for a heat transfer tube

by Taehwan Ahn, Jinhoon Kang, Jae Jun Jeong, Byongjo Yun
Published 2019-10-01

Modification of the fast fourier transform-based method by signal mirroring for accuracy quantification of thermal-hydraulic system code

by Tae Wook Ha, Jae Jun Jeong, Ki Yong Choi
Published 2017-08-01

Void fraction prediction for separated flows in the nearly horizontal tubes

by Tae-Hwan Ahn, Byong-Jo Yun, Jae-Jun Jeong
Published 2015-10-01

Improvement of the MARS subcooled boiling model for a vertical upward flow

by Tae-Wook Ha, Jae Jun Jeong, Byong-Jo Yun
Published 2019-07-01

Numerical prediction of transient hydraulic loads acting on PWR steam generator tubes and supports during blowdown following a feedwater line break

by Jong Chull Jo, Jae Jun Jeong, Byong Jo Yun, Jongkap Kim
Published 2021-01-01

Development of Bubble Size Correlation for Adiabatic Forced Convective Bubbly Flow in Low Pressure Condition Using CFD Code

by Jinyeong Bak, Huiyung Kim, Jae Jun Jeong, Dongjin Euh, Byongjo Yun
Published 2020-08-01

DEVELOPMENT OF A COMPUTER PROGRAM TO SUPPORT AN EFFICIENT NON-REGRESSION TEST OF A THERMAL-HYDRAULIC SYSTEM CODE

by JUN YEOB LEE, JAESEUNG SUH, KYUNG DOO KIM, JAE JUN JEONG
Published 2014-10-01

Numerical prediction of a flashing flow of saturated water at high pressure

by Jong Chull Jo, Jae Jun Jeong, Byong Jo Yun, Frederick J. Moody
Published 2018-10-01

IMPROVEMENT OF THE LOCA PSA MODEL USING A BEST-ESTIMATE THERMAL-HYDRAULIC ANALYSIS

by DONG HYUN LEE, HO-GON LIM, HAN YOUNG YOON, JAE JUN JEONG
Published 2014-08-01

Assessment of the MARS Code Using the Two-Phase Natural Circulation Experiments at a Core Catcher Test Facility

by Dong Hun Lee, Su Ryong Choi, Kwang Soon Ha, Han Young Yoon, Jae Jun Jeong
Published 2017-01-01

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

by HAN YOUNG YOON, JAE RYONG LEE, HYUNGRAE KIM, IK KYU PARK, CHUL-HWA SONG, HYOUNG KYU CHO, JAE JUN JEONG
Published 2014-10-01