Zobrazeno 1 - 8
of 8
pro vyhledávání: '"Chul-Gyo Seo"'
Autor:
Jong Man Park, Young Wook Tahk, Yong Jin Jeong, Kyu Hong Lee, Heemoon Kim, Yang Hong Jung, Boung-Ok Yoo, Young Gwan Jin, Chul Gyo Seo, Seong Woo Yang, Hyun Jung Kim, Jeong Sik Yim, Yeon Soo Kim, Bei Ye, Gerard L. Hofman
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 5, Pp 1044-1062 (2017)
The construction project of the Kijang research reactor (KJRR), which is the second research reactor in Korea, has been launched. The KJRR was designed to use, for the first time, U–Mo fuel. Plate-type U–7 wt.% Mo/Al–5 wt.% Si, referred to as U
Externí odkaz:
https://doaj.org/article/7140bf7e3be84fa780c11713c8904f2f
Autor:
Myung-Hwan Wi, Jaehyuk Eoh, Jeong-Ik Lee, Hee Taek Chae, Hwa-Young Jung, Yong Hwan Yoo, Chul Gyo Seo
Publikováno v:
Nuclear Engineering and Design. 320:235-249
In a sodium-cooled fast reactor, a sodium-water reaction (SWR) could be occurred at pressure boundaries between the two separated systems, the steam Rankine cycle and the sodium coolant system, which results in a serious problem in the system. Since
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0220758120291ba7a8c5474cfdf4f56d
https://doi.org/10.1016/j.nucengdes.2017.06.002
https://doi.org/10.1016/j.nucengdes.2017.06.002
Autor:
Young Wook Tahk, Hyun-Jung Kim, Boung-Ok Yoo, Yang Hong Jung, Young Gwan Jin, Gerard L. Hofman, Kyu Hong Lee, Seong Woo Yang, Bei Ye, Jeong sik Yim, Jong Man Park, Heemoon Kim, Yeon Soo Kim, Jeong Yong Jin, Chul Gyo Seo
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 5, Pp 1044-1062 (2017)
The construction project of the Kijang research reactor (KJRR), which is the second research reactor in Korea, has been launched. The KJRR was designed to use, for the first time, U–Mo fuel. Plate-type U–7 wt.% Mo/Al–5 wt.% Si, referred to as U
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::116e0921ebaf63e32fd2b3a883d8d20d
https://doi.org/10.1016/j.net.2017.04.003
https://doi.org/10.1016/j.net.2017.04.003
Autor:
Chul Gyo Seo, Daeseong Jo
Publikováno v:
Progress in Nuclear Energy. 81:16-21
To investigate the effects of transverse power distribution on fuel temperature, a two-dimensional thermal analysis model was developed in this study. An equilibrium reactor core with 22 fuel assemblies facilitated with plate-type fuel was modeled us
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::34d04eb535c527d909743753bdfa29ea
https://doi.org/10.1016/j.pnucene.2014.12.017
https://doi.org/10.1016/j.pnucene.2014.12.017
Publikováno v:
Nuclear Technology and Radiation Protection, Vol 30, Iss 1, Pp 55-60 (2015)
A sensitivity analysis of a point kernel code was performed to investigate the effect of mesh division of a volume source on the radiation flux at points of interest. The QAD-CGGP, known as a representative point kernel code, was employed for a serie
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::3d599b611f588889d8f2798ad07fa620
http://www.doiserbia.nb.rs/img/doi/1451-3994/2015/1451-39941501055K.pdf
http://www.doiserbia.nb.rs/img/doi/1451-3994/2015/1451-39941501055K.pdf
Autor:
Chul-Gyo Seo, Nhi Dien Nguyen, Hai Dang Vo Doan, Haksung Kim, Vinh Vinh Le, Ton Nghiem Huynh, Cheol Park
Publikováno v:
Nuclear Science and Technology. 4:26-35
This paper presents some of studied results of a pre-feasibility project on a new research reactor for Vietnam. In this work, two conceptual nuclear designs of 20 MW multi-purpose research reactor have been done. The reference reactor is the light wa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5255c406eed73ce9783880de13c0d1bb
https://doi.org/10.53747/jnst.v4i1.210
https://doi.org/10.53747/jnst.v4i1.210
Autor:
Nam Zin Cho, Chul Gyo Seo
Publikováno v:
Nuclear Engineering and Design. 252:34-41
A new core design concept for multi-purpose research reactors is presented. New concept cores using material test reactor (MTR) type fuel are constructed with the edge trimmed in-core irradiation hole. Conventional research reactors have core configu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::355c85a6aacc4354e55018305362c2dd
https://doi.org/10.1016/j.nucengdes.2012.06.031
https://doi.org/10.1016/j.nucengdes.2012.06.031
Publikováno v:
Volume 3: Thermal Hydraulics; Instrumentation and Controls.
The conceptual thermal hydraulic design analyses for a 20 MW reference AHR core have been jointly performed by KAERI and DNRI (VAEC). The preliminary core thermal hydraulic characteristics and the safety margins for the AHR core were studied for vari
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b7485242b5ae79656418372b02ddfb4a
https://doi.org/10.1115/icone16-48157
https://doi.org/10.1115/icone16-48157