Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea
Yoo, Jaewoon, Chang, Jinwook, Lim, Jae-Yong, Cheon, Jin-Sik, Lee, Tae-Ho, Kim, Sung Kyun, Lee, Kwi Lim, Joo, Hyung-Kook
Published in Nuclear engineering and technology (01.10.2016)
Published in Nuclear engineering and technology (01.10.2016)
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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)
Get full text
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)
Get full text
Published in Nuclear engineering and technology (2016)
Journal Article
Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea
Yoo, Jaewoon, Chang, Jinwook, Lim, Jae-Yong, Cheon, Jin-Sik, Lee, Tae-Ho, Kim, Sung Kyun, Lee, Kwi Lim, Joo, Hyung-Kook
Published in Nuclear engineering and technology (2016)
Get full text
Published in Nuclear engineering and technology (2016)
Journal Article
Neutron balance approach for inline critical rod position search calculation in Monte Carlo reactor analysis
Jo, YuGwon, Yoo, Jaewoon, Lim, Jae-Yong
Published in Nuclear engineering and technology (01.07.2024)
Published in Nuclear engineering and technology (01.07.2024)
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Journal Article
Assessment of tritium effluent from Prototype Generation IV Sodium-cooled Fast Reactor
Kim, Taek K., Lim, Jaeyong, Lee, Minjae, Yoo, Jaewoon, Grandy, C.
Published in Annals of nuclear energy (01.09.2021)
Published in Annals of nuclear energy (01.09.2021)
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Journal Article
Assessment of tritium effluent from Prototype Generation IV Sodium-cooled Fast Reactor
Kim, Taek K., Lim, Jaeyong, Lee, Minjae, Yoo, Jaewoon, Grandy, C.
Published in Annals of nuclear energy (24.04.2021)
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Published in Annals of nuclear energy (24.04.2021)
Journal Article
Conceptual design of compact supercritical water-cooled fast reactor with thermal hydraulic coupling
Yoo, Jaewoon, Ishiwatari, Yuki, Oka, Yoshiaki, Liu, Jie
Published in Annals of nuclear energy (01.08.2006)
Published in Annals of nuclear energy (01.08.2006)
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Journal Article
Subchannel analysis of supercritical light water-cooled fast reactor assembly
Yoo, Jaewoon, Oka, Yoshiaki, Ishiwatari, Yuki, Yang, Jue, Liu, Jie
Published in Nuclear engineering and design (01.05.2007)
Published in Nuclear engineering and design (01.05.2007)
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Journal Article
A Conformal mapped nodal SP 3 method for hexagonal core analysis
Kim, Yeong-il, Yoo, Jaewoon, Hahn, Dohee, Kim, Chang Hyo
Published in Annals of nuclear energy (2009)
Published in Annals of nuclear energy (2009)
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Journal Article
A Conformal mapped nodal SP3 method for hexagonal core analysis
Kim, Yeong-il, Yoo, Jaewoon, Hahn, Dohee, Kim, Chang Hyo
Published in Annals of nuclear energy (01.05.2009)
Published in Annals of nuclear energy (01.05.2009)
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Journal Article
Thermo-mechanical analysis of supercritical pressure light water-cooled fast reactor fuel rod by FEMAXI-6 code
Yoo, Jaewoon, Oka, Yoshiaki, Ishiwatari, Yuki, Liu, Jie
Published in Annals of nuclear energy (01.11.2006)
Published in Annals of nuclear energy (01.11.2006)
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Journal Article