Zobrazeno 1 - 10
of 198
pro vyhledávání: '"Kyoung Ho Kang"'
Autor:
Jin-Hwa Yang, Tae-Hwan Ahn, Hong Hyun Son, Jin Su Kwon, Hwang Bae, Hyun-Sik Park, Kyoung-Ho Kang
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 3, Pp 1066-1080 (2024)
SMART100 has a containment pressure and radioactivity suppression system (CPRSS) for passive containment cooling system (PCCS). This prevents overheating and over-pressurization of a containment through direct contact condensation in an in-containmen
Externí odkaz:
https://doaj.org/article/f8d31be31cbb4aafa5adb11faef76f37
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 7, Pp 2438-2446 (2023)
To cool down a nuclear reactor core and prevent the fuel damage without a pump-driven active component during any anticipated accident, the passive emergency core cooling system (PECCS) was designed and adopted in an advanced light water reactor, i-P
Externí odkaz:
https://doaj.org/article/3153f1a970cb47dc9b3600ac3b6bdf9b
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 8, Pp 2477-2487 (2021)
To improve safety analysis technology for a nuclear reactor containment considering an interaction between a reactor coolant system (RCS) and containment, this study aims at an experimental investigation on the integrated simulation of the RCS and co
Externí odkaz:
https://doaj.org/article/b59ebefb0164475ca5e2cc401d1c5288
Autor:
Jongrok Kim, Byoung-Uhn Bae, Yusun Park, Jae Bong Lee, Nam-Hyun Choi, Seok Cho, Kyoung-Ho Kang
Publikováno v:
Energies, Vol 15, Iss 9, p 3189 (2022)
The advanced thermal-hydraulic test loop for accident simulation (ATLAS) was developed and operated at The Korea Atomic Energy Research Institute. The ATLAS is operated to simulate accidents in pressurized water reactors (PWRs). A domestic standard p
Externí odkaz:
https://doaj.org/article/8c3375d025e043b58eeb96d8fb0f6544
Publikováno v:
Frontiers in Energy Research, Vol 8 (2020)
An experimental simulation for a loss of coolant accident with a 4-in cold leg top-slot break was performed using ATLAS, an integral effect test facility at the Korea Atomic Energy Research Institute (KAERI), South Korea. The aims of this test are to
Externí odkaz:
https://doaj.org/article/391875ad9eba4b329488134f14da8bc5
Autor:
YEON-SIK KIM, KI-YONG CHOI, SEOK CHO, HYUN-SIK PARK, KYOUNG-HO KANG, CHUL-HWA SONG, WON-PIL BAEK
Publikováno v:
Nuclear Engineering and Technology, Vol 45, Iss 7, Pp 871-894 (2013)
KAERI (Korea Atomic Energy Research Institute) has been operating an integral effect test facility, the Advanced Thermal-Hydraulic Test Loop for Accident Simulation (ATLAS), for transient and accident simulations of advanced pressurized water reactor
Externí odkaz:
https://doaj.org/article/79a8ab89124945e2a6b01b0396577b2f
Publikováno v:
Nuclear Engineering and Technology, Vol 45, Iss 6, Pp 759-766 (2013)
As passive safety features for nuclear power plants receive increasing attention, various studies have been conducted to develop safety systems for 3rd-generation (GEN-III) nuclear power plants that are driven by passive systems. The Passive Auxiliar
Externí odkaz:
https://doaj.org/article/9ce023b75acc4982bdd435f2ef93fce7
Publikováno v:
Nuclear Engineering and Technology, Vol 45, Iss 2, Pp 179-190 (2013)
A station blackout experiment called SBO-01 was performed at the ATLAS facility. From the SBO-01 test, the station blackout scenario can be characterized into two typical phases: A first phase characterized by decay heat removal through secondary saf
Externí odkaz:
https://doaj.org/article/b35b7a2589b146d2960bd5c0e4950137
Publikováno v:
Nuclear Technology. 207:680-691
To investigate thermal-hydraulic phenomena during an intermediate-break loss-of-coolant accident (IBLOCA) and evaluate the effect of a direct vessel injection (DVI) line break, an integral effect t...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::162db7a69bfd5b57a3876251797fdbd9
https://doi.org/10.1080/00295450.2020.1796078
https://doi.org/10.1080/00295450.2020.1796078
Comparison of loop seal clearing behavior between SBLOCA and SBO-related tests in the ATLAS facility
Autor:
Yeon-Sik Kim, Kyoung-Ho Kang
Publikováno v:
Annals of Nuclear Energy. 132:734-740
Loop seal clearing (LSC) behavior was investigated for small-break loss-of-coolant accident (SBLOCA) and station blackout (SBO)-related tests in the Advanced Thermal-Hydraulic Test Loop for Accident Simulation (ATLAS) facility. Major characteristics
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3c77b2cee7d28598de8cd6b8e315bdb6
https://doi.org/10.1016/j.anucene.2019.06.065
https://doi.org/10.1016/j.anucene.2019.06.065