Zobrazeno 1 - 10
of 52
pro vyhledávání: '"Sung-Jae Yi"'
Autor:
Byong Guk Jeon, Eunkoo Yun, Hwang Bae, Jin-Hwa Yang, Sung-Uk Ryu, Yun-Gon Bang, Sung-Jae Yi, Hyun-Sik Park
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 3, Pp 826-833 (2022)
A two-phase natural circulation test using SMART integral test loop (SMART–ITL) was conducted to explore thermo-hydraulic phenomena of two-phase natural circulation in the SMART reactor. Specifically, the test examined the natural circulation in th
Externí odkaz:
https://doaj.org/article/72d3593270994b2a894a2c9948b818b7
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 7, Pp 1537-1546 (2017)
Many thermal–hydraulic tests have been conducted at the Korea Atomic Energy Research Institute for verification of the SMART (System-integrated Modular Advanced ReacTor) design, the standard design approval of which was issued by the Korean regulat
Externí odkaz:
https://doaj.org/article/e313ceafda764cd1bb5b4f3d14586d21
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 5, Pp 968-978 (2017)
Three small-break loss-of-coolant accident (SBLOCA) tests with safety injection pumps were carried out using the integral-effect test loop for SMART (System-integrated Modular Advanced ReacTor), i.e., the SMART-ITL facility. The types of break are a
Externí odkaz:
https://doaj.org/article/56dd32559f59471ca3c4b5c290fd54d0
Publikováno v:
Nuclear Engineering and Technology, Vol 48, Iss 1, Pp 268-273 (2016)
An innovative safety concept for a light water reactor has been developed at the Korea Atomic Energy Research Institute. It is a unique concept that adopts both a fast heat transfer mechanism for a small containment and a changing mechanism of the co
Externí odkaz:
https://doaj.org/article/1dd492b3b3ad4f38a997cd5493f4788e
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2014 (2014)
To validate the performance and safety of an integral type reactor of SMART, a thermal-hydraulic integral effect test facility, VISTA-ITL, is introduced with a discussion of its scientific design characteristics. The VISTA-ITL was used extensively to
Externí odkaz:
https://doaj.org/article/deba0368bbbb46da977dff4b82e89d75
Autor:
Sung-Jae Yi, Byong Guk Jeon, Hyun-Sik Park, Sung-Uk Ryu, Eunkoo Yun, Jin-Hwa Yang, Hwang Bae, Yun-Gon Bang
Publikováno v:
Nuclear Engineering and Technology. 54:826-833
A two-phase natural circulation test using SMART integral test loop (SMART–ITL) was conducted to explore thermo-hydraulic phenomena of two-phase natural circulation in the SMART reactor. Specifically, the test examined the natural circulation in th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::afa49814a941516132c4813f334efa39
https://doi.org/10.1016/j.net.2021.09.011
https://doi.org/10.1016/j.net.2021.09.011
Autor:
Byong Guk Jeon, Hwang Bae, Su-Hyeon Kim, Jin-Hwa Yang, Sung-Uk Ryu, Sung-Jae Yi, Hyun-Sik Park
Publikováno v:
Annals of Nuclear Energy. 188:109835
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::df810c833e44f53b55e545e75e3a6763
https://doi.org/10.1016/j.anucene.2023.109835
https://doi.org/10.1016/j.anucene.2023.109835
Publikováno v:
Nuclear Technology. 206:1421-1435
Even for small modular reactors (SMRs) with all large pipes removed, a small-break loss-of-coolant accident (SBLOCA) is an important design-basis accident (DBA). Experimental simulation of the SBLO...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::158160adf84a2983955db8bf8a80ce6b
https://doi.org/10.1080/00295450.2020.1775450
https://doi.org/10.1080/00295450.2020.1775450
Autor:
Sung Uk Ryu, Byong-Guk Jeon, Eunkoo Yun, Jin-Hwa Yang, Sung-Jae Yi, Hyun-Sik Park, Hwang Bae, Yun-Gon Bang
Publikováno v:
Annals of Nuclear Energy. 126:10-19
The passive injection characteristics of the core makeup tank (CMT) of the SMART (System-integrated Modular Advanced ReacTor) were experimentally investigated using the integral-effect test loop, i.e., the SMART-ITL facility, for three kinds of accid
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4b4ac5afc8400b4c73899ac3642841d0
https://doi.org/10.1016/j.anucene.2018.11.002
https://doi.org/10.1016/j.anucene.2018.11.002
Publikováno v:
Annals of Nuclear Energy. 123:110-118
This paper reports an experimental research on the performance of the passive emergency core cooling system (PECCS) using an integral effect test facility in Korea Atomic Energy Research Institute (KAERI). The PECCS consists of two hybrid safety inje
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f406f114c85ffc14849e50067d477044
https://doi.org/10.1016/j.anucene.2018.09.023
https://doi.org/10.1016/j.anucene.2018.09.023