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)
Get full text
Journal Article
RANS based CFD methodology for a real scale 217-pin wire-wrapped fuel assembly of KAERI PGSFR
Jeong, Jae-Ho, Song, Min-Seop, Lee, Kwi-Lim
Published in Nuclear engineering and design (01.03.2017)
Published in Nuclear engineering and design (01.03.2017)
Get full text
Journal Article
CFD investigation of three-dimensional flow phenomena in a JAEA 127-pin wire-wrapped fuel assembly
Jeong, Jae-Ho, Song, Min-Seop, Lee, Kwi-Lim
Published in Nuclear engineering and design (01.11.2017)
Published in Nuclear engineering and design (01.11.2017)
Get full text
Journal Article
Thermal-hydraulic effect of wire spacer in a wire-wrapped fuel bundles for SFR
Jeong, Jae-Ho, Song, Min-Seop, Lee, Kwi-Lim
Published in Nuclear engineering and design (15.08.2017)
Published in Nuclear engineering and design (15.08.2017)
Get full text
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 (2015)
Get full text
Published in Nuclear engineering and technology (2015)
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)
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
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 (01.10.2016)
Published in Nuclear engineering and technology (01.10.2016)
Get full text
Journal Article
Design evaluation of large-scale sodium integral effect test facility (STELLA-2) using MARS-LMR
Lee, Jewhan, Eoh, Jaehyuk, Kim, Hyungmo, Yoon, Jung, Lee, Yong-Bum, Kim, Eui-Kwang, Jeong, Jae-Ho, Lee, Kwi Lim, Jeong, Ji-Young
Published in Annals of nuclear energy (01.10.2018)
Published in Annals of nuclear energy (01.10.2018)
Get full text
Journal Article
The sensitivity analysis for IHTS and SG due to the Large-scale Sodium-Water Reaction event in PGSFR
Ahn, Sang June, Park, Gun Yeop, Lee, Kwi Lim, Choi, Chiwoong, Jeong, Taekyeong, Kim, Jin Tae, Lee, Seung Won, Jeong, Jae-Ho
Published in Annals of nuclear energy (01.08.2018)
Published in Annals of nuclear energy (01.08.2018)
Get full text
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)
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 (01.10.2016)
Published in Nuclear engineering and technology (01.10.2016)
Get full text
Journal Article
PASSIVE DECAY HEAT REMOVAL SYSTEM USING ORGANOIC FLUID, METHOD OF DRIVING HEAT REMOVAL SYSTEM
CHANG, WON PYO, LEE, KWI LIM, JEONG, HAE YONG, HA, KWI SEOK, CHOI, CHI WOONG, KANG, SEOK HUN
Year of Publication 27.01.2014
Get full text
Year of Publication 27.01.2014
Patent