Validation of interfacial area concentration model for simulating bubbly and cap/slug flow behaviors in large diameter pipes using LSTF, ATLAS, and horizontal pipe experiment data
Heo, Jaeseok, Yoon, Seung Hyun, Kim, Kyung Doo, Ha, Kwi-Seok, Hibiki, Takashi
Published in Progress in nuclear energy (New series) (01.10.2020)
Published in Progress in nuclear energy (New series) (01.10.2020)
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Journal Article
Three-dimensional flow phenomena in a wire-wrapped 37-pin fuel bundle for SFR
Jeong, Jae-Ho, Yoo, Jin, Lee, Kwi-Lim, Ha, Kwi-Seok
Published in Nuclear engineering and technology (01.08.2015)
Published in Nuclear engineering and technology (01.08.2015)
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Journal Article
Evaluation of a Sodium–Water Reaction Event Caused by Steam Generator Tubes Break in the Prototype Generation IV Sodium-cooled Fast Reactor
Ahn, Sang June, Ha, Kwi-Seok, Chang, Won-Pyo, Kang, Seok Hun, Lee, Kwi Lim, Choi, Chi-Woong, Lee, Seung Won, Yoo, Jin, Jeong, Jae-Ho, Jeong, Taekyeong
Published in Nuclear engineering and technology (01.08.2016)
Published in Nuclear engineering and technology (01.08.2016)
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Journal Article
A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor
Lee, Kwi Lim, Ha, Kwi-Seok, Jeong, Jae-Ho, Choi, Chi-Woong, Jeong, Taekyeong, Ahn, Sang June, Lee, Seung Won, Chang, Won-Pyo, Kang, Seok Hun, Yoo, Jaewoon
Published in Nuclear engineering and technology (01.10.2016)
Published in Nuclear engineering and technology (01.10.2016)
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Journal Article
Fuel fragmentation and relocation (FFR) model in SPACE code PART 1: Development and verification
Choi, Chiwoong, Lee, Seung-wook, Lee, Jong-hyuk, Heo, Jaeseok, You, Byung-hyun, won Bae, Sung, Ha, Kwi-seok, Kim, Kyung Doo
Published in Annals of nuclear energy (01.05.2024)
Published in Annals of nuclear energy (01.05.2024)
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Journal Article
Sensitivity and uncertainty analysis for ULOF of PGSFR using PAPIRUS
Kang, Sarah, Choi, ChiWoong, Ha, Kwi-Seok, Heo, Jaeseok
Published in Annals of nuclear energy (01.12.2017)
Published in Annals of nuclear energy (01.12.2017)
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Journal Article
Evaluation of a Sodium-Water Reaction Event Caused by Steam Generator Tubes Break in the Prototype Generation IV Sodium-cooled Fast Reactor
Ahn, Sang June, Ha, Kwi-Seok, Chang, Won-Pyo, Kang, Seok Hun, Lee, Kwi Lim, Choi, Chi-Woong, Lee, Seung Won, Yoo, Jin, Jeong, Jae-Ho, Jeong, Taekyeong
Published in Nuclear engineering and technology (2016)
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Published in Nuclear engineering and technology (2016)
Journal Article
A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor
Lee, Kwi Lim, Ha, Kwi-Seok, Jeong, Jae-Ho, Choi, Chi-Woong, Jeong, Taekyeong, Ahn, Sang June, Lee, Seung Won, Chang, Won-Pyo, Kang, Seok Hun, Yoo, Jaewoon
Published in Nuclear engineering and technology (2016)
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Published in Nuclear engineering and technology (2016)
Journal Article
Assessment study about the risk of Wilks' formula for uncertainty quantification of design extension condition scenarios in prototype Gen-IV sodium fast reactor
Kang, Sarah, Heo, Jaeseok, Choi, ChiWoong, Ha, Kwi-Seok, Bae, Sung Won
Published in Journal of nuclear science and technology (03.07.2018)
Published in Journal of nuclear science and technology (03.07.2018)
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Journal Article
A ‘must-go path’ scenario for sustainable development and the role of nuclear energy in the 21st century
Jeong, Hae-Yong, Kim, Young-In, Lee, Yong-Bum, Ha, Kwi-Seok, Won, Byung-Chool, Lee, Dong-Uk, Hahn, Dohee
Published in Energy policy (01.04.2010)
Published in Energy policy (01.04.2010)
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Journal Article
Simulation of the EBR-II Loss-of-Flow Tests Using the MARS Code
Ha, Kwi-Seok, Jeong, Hae-Yong, Cho, Chungho, Kwon, Young-Min, Lee, Yong-Bum, Hahn, Dohee
Published in Nuclear technology (01.02.2010)
Published in Nuclear technology (01.02.2010)
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Journal Article
Evaluation of the conduction shape factor with a CFD code for a liquid–metal heat transfer in heated triangular rod bundles
Jeong, Hae-yong, Ha, Kwi-seok, Kwon, Young-min, Lee, Yong-bum, Hahn, Dohee, Cahalan, James E., Dunn, Floyd E.
Published in Nuclear engineering and design (01.03.2007)
Published in Nuclear engineering and design (01.03.2007)
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Journal Article
Modeling of Flow Blockage in a Liquid Metal-Cooled Reactor Subassembly with a Subchannel Analysis Code
Jeong, Hae-Yong, Ha, Kwi-Seok, Chang, Won-Pyo, Kwon, Young-Min, Lee, Yong-Bum
Published in Nuclear technology (01.01.2005)
Published in Nuclear technology (01.01.2005)
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Journal Article