Zobrazeno 1 - 10
of 17
pro vyhledávání: '"Kwi Lim Lee"'
Autor:
Jaewoon Yoo, Jinwook Chang, Jae-Yong Lim, Jin-Sik Cheon, Tae-Ho Lee, Sung Kyun Kim, Kwi Lim Lee, Hyung-Kook Joo
Publikováno v:
Nuclear Engineering and Technology, Vol 48, Iss 5, Pp 1059-1070 (2016)
The Prototype Gen IV sodium cooled fast reactor (PGSFR) has been developed for the last 4 years, fulfilling the technology demonstration of the burning capability of transuranic elements included in light water reactor spent nuclear fuel. The PGSFR d
Externí odkaz:
https://doaj.org/article/f27179e57bc14584886f5b53f81afae4
Autor:
Kwi Lim Lee, Kwi-Seok Ha, Jae-Ho Jeong, Chi-Woong Choi, Taekyeong Jeong, Sang June Ahn, Seung Won Lee, Won-Pyo Chang, Seok Hun Kang, Jaewoon Yoo
Publikováno v:
Nuclear Engineering and Technology, Vol 48, Iss 5, Pp 1071-1082 (2016)
Korea Atomic Energy Research Institute has been developing a pool-type sodium-cooled fast reactor of the Prototype Gen-IV Sodium-cooled Fast Reactor (PGSFR). To assess the effectiveness of the inherent safety features of the PGSFR, the system transie
Externí odkaz:
https://doaj.org/article/b61623e92bee486d939401d6ecb3c021
Autor:
Sang June Ahn, Kwi-Seok Ha, Won-Pyo Chang, Seok Hun Kang, Kwi Lim Lee, Chi-Woong Choi, Seung Won Lee, Jin Yoo, Jae-Ho Jeong, Taekyeong Jeong
Publikováno v:
Nuclear Engineering and Technology, Vol 48, Iss 4, Pp 952-964 (2016)
The prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Korea Atomic Energy Research Institute. This reactor uses sodium as a reactor coolant to transfer the core heat energy to the turbine. Sodium has chemical charac
Externí odkaz:
https://doaj.org/article/6dd18ad0b05c465fb8f636e7ba6daf05
Autor:
Yong-Bum Lee, Jewhan Lee, Eui-Kwang Kim, Kwi Lim Lee, Ji-Young Jeong, Hyungmo Kim, Jae-Ho Jeong, Jae-Hyuk Eoh, Jung Yoon
Publikováno v:
Annals of Nuclear Energy. 120:845-856
The STELLA program is one of the key activities to support the development of PGSFR in Korea and the target is the DHRS. The STELLA-2 facility is an integral effect test facility and scaled-down components of PGSFR are included. For the STELLA-2 desi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bd50fcde6a25ecfb9f6cecb2b033b506
https://doi.org/10.1016/j.anucene.2018.07.006
https://doi.org/10.1016/j.anucene.2018.07.006
Publikováno v:
Nuclear Engineering and Design. 323:166-184
This paper presents a RANS (Reynolds Averaged Navier-Stokes simulation) based CFD (Computational Fluid Dynamics) investigation of the three-dimensional flow phenomena in a JAEA (Japan Atomic Energy Agency) 127-pin wire-wrapped fuel assembly. Complica
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ffaaa14497dad986371af36d22ac6084
https://doi.org/10.1016/j.nucengdes.2017.08.008
https://doi.org/10.1016/j.nucengdes.2017.08.008
Publikováno v:
Nuclear Engineering and Design. 313:470-485
This paper presents a suitable way for a practical RANS (Reynolds Averaged Navier-Stokes simulation) based CFD (Computational Fluid Dynamics) methodology which is applicable to real scale 217-pin wire-wrapped fuel assembly of KAERI (Korea Atomic Ener
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::39c2f7dd776d9a2109d3f7545cdfc76a
https://doi.org/10.1016/j.nucengdes.2017.01.007
https://doi.org/10.1016/j.nucengdes.2017.01.007
Autor:
Kwi Lim Lee, Jae-Yong Lim, Tae-Ho Lee, Jaewoon Yoo, Sung-Kyun Kim, Jin-Sik Cheon, Hyung-Kook Joo, Jinwook Chang
Publikováno v:
Nuclear Engineering and Technology, Vol 48, Iss 5, Pp 1059-1070 (2016)
The Prototype Gen IV sodium cooled fast reactor (PGSFR) has been developed for the last 4 years, fulfilling the technology demonstration of the burning capability of transuranic elements included in light water reactor spent nuclear fuel. The PGSFR d
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::c51da165b51d2af22079dda30fc53008
Autor:
Won-Pyo Chang, Chiwoong Choi, Jin Yoo, Seok Hun Kang, Taekyeong Jeong, Sang June Ahn, Seung Won Lee, Kwi-Seok Ha, Kwi Lim Lee, Jae-Ho Jeong
Publikováno v:
Nuclear Engineering and Technology, Vol 48, Iss 4, Pp 952-964 (2016)
The prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Korea Atomic Energy Research Institute. This reactor uses sodium as a reactor coolant to transfer the core heat energy to the turbine. Sodium has chemical charac
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::5877db6f903cdb4465133d8b2747be86
Publikováno v:
Nuclear Engineering and Technology, Vol 47, Iss 5, Pp 523-533 (2015)
Three-dimensional flow phenomena in a wire-wrapped 37-pin fuel assembly mock-up of a Japanese loop-type sodium-cooled fast reactor, Monju, were investigated with a numerical analysis using a general-purpose commercial computational fluid dynamics cod
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2e67e6bcef225188f100f7057af43b8a
https://doi.org/10.1016/j.net.2015.06.001
https://doi.org/10.1016/j.net.2015.06.001
Autor:
Kwi Lim Lee, Soon Heung Chang
Publikováno v:
Nuclear Engineering and Design. 240:3397-3404
An experimental study was performed using R-134a in an annulus channel to investigate the heat transfer characteristics in the post-CHF region. The experiments were conducted under the outlet pressures of 1.1–2.0 MPa, the mass fluxes of 100–400 k
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f9efeafac3496a67b5470c959738fcd5
https://doi.org/10.1016/j.nucengdes.2010.07.013
https://doi.org/10.1016/j.nucengdes.2010.07.013