Zobrazeno 1 - 10
of 15
pro vyhledávání: '"DongGun Son"'
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2023 (2023)
As an integrated computer code development for severe accident sequence analysis in Korea, CINEMA has been developing from an initiation event to a containment failure. The CINEMA computer code is composed of CSPACE, SACAP, and SIRIUS, which are capa
Externí odkaz:
https://doaj.org/article/2c5ec480b71542f8806460f4f0d9eb27
Autor:
Donggun Son, Jungil Lee
Publikováno v:
Mathematics, Vol 11, Iss 3, p 706 (2023)
In the present study, we propose a periodically rotating distributed forcing for turbulent flow over a sphere for its drag reduction. The blowing/suction forcing is applied on a finite slot of the sphere surface near the flow separation, and unsteady
Externí odkaz:
https://doaj.org/article/33f6b1790c8b4447a46ba736529f7a36
Publikováno v:
Nuclear Engineering and Technology, Vol 48, Iss 4, Pp 932-940 (2016)
Pool boiling heat transfer of water saturated at atmospheric pressure was investigated experimentally on Cu surfaces with high-temperature, thermally-conductive, microporous coatings (HTCMC). The coatings were created by sintering Cu powders on Cu su
Externí odkaz:
https://doaj.org/article/4db872b6aa9c478caedcfe18f6b8397e
Autor:
JinHo Song, DongGun Son, JaeHyun Ham, JunHo Bae, SungWon Bae, Kwangsoon Ha, ByungJo Kim, Sun Hong Yoon, BubDong Chung, SoonHo Park, ChangHwan Park, JaeHwan Park, YuJung Choi
Publikováno v:
Nuclear Engineering and Design. 404:112181
Publikováno v:
Annals of Nuclear Energy. 181:109529
Autor:
Haecheon Choi, Donggun Son
Publikováno v:
IEEE Transactions on Control Systems Technology. 27:1385-1396
In this paper, we numerically perform a feedback gain optimization of the proportional-integral-differential (PID) control of flows over a circular cylinder at Re = 60 and 100. We measure the transverse velocity at a centerline location in the wake a
Publikováno v:
Annals of Nuclear Energy. 161:108463
An IVR (In-Vessel corium Retention) through ERVC (External Reactor Vessel Cooling) is known to be an effective means for maintaining the reactor vessel integrity during severe accidents in nuclear power plants. The evaluation method of the IVR-ERVC f
Publikováno v:
Transactions of the American Nuclear Society - Volume 121.
Autor:
Jungil Lee, Donggun Son
Publikováno v:
Journal of Mechanical Science and Technology. 30:3667-3672
In the present study, we perform a proportional feedback control of laminar flow over a hemisphere at Re = 300 to reduce its lift fluctuations by attenuating the strength of the vortex shedding. As a control input, blowing/suction is distributed on t
Publikováno v:
Nuclear Engineering and Technology, Vol 48, Iss 4, Pp 932-940 (2016)
Pool boiling heat transfer of water saturated at atmospheric pressure was investigated experimentally on Cu surfaces with high-temperature, thermally-conductive, microporous coatings (HTCMC). The coatings were created by sintering Cu powders on Cu su