Zobrazeno 1 - 9
of 9
pro vyhledávání: '"Myung-Hwan Wi"'
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
Publikováno v:
Korean Chemical Engineering Research. 54:863-870
본 논문의 목적은 소듐냉각고속로(sodium cooled fast reactor, SFR)와 초임계 CO2 Brayton cycle의 연계 시, 원자로 열수송 계통과 동력변환 계통의 압력 경계를 형성하는 회로인쇄형 열교환기의 경계면
Publikováno v:
Nuclear Engineering and Design. 297:158-165
One of the promising future nuclear energy systems, the Sodium-cooled Fast Reactor (SFR) has been actively developed internationally. Recently, to improve safety and economics of a SFR further, coupling supercritical CO2 power cycle was suggested. Ho
Autor:
Myung Hwan Wi, Eui Kwang Kim, Jaehyuk Eoh, Chung Ho Cho, Kwi Seok Ha, Yonghee Kim, Sang Ji Kim, Jong Bum Kim, Ser Gi Hong
Publikováno v:
Nuclear Technology. 170:148-158
The conceptual design of a 900-MW(thermal) lead-cooled fast reactor (LFR) system for transuranic element (TRU) burning is developed and analyzed using TRU-U-Zr metallic alloy fuel. The design and a...
Publikováno v:
Nuclear Technology. 152:223-238
A computational study of thermal striping in an upper plenum of the Korea Advanced Liquid-Metal Reactor (KALIMER) was performed. The primary objective of the present study was to find the distribution of the amplitude of temperature fluctuation in th
Publikováno v:
KSME International Journal. 18:1782-1798
A numerical study of a natural convection in a rectangular cavity with the low-Reynoldsnumber differential stress and flux model is presented. The primary emphasis of the study is placed on the investigation of the accuracy and numerical stability of
Publikováno v:
Volume 4: Fluid Structure Interaction.
A computational study for the evaluation of the current turbulence models for the prediction of a thermal striping in a triple-jet is performed. The tested turbulence models are the two-layer model, the shear stress transport model and the elliptic r
Publikováno v:
Problems Involving Thermal Hydraulics, Liquid Sloshing, and Extreme Loads on Structures.
A computational study of thermal striping in an upper plenum of KALIMER (Korea Advanced Liquid Metal Reactor) is performed. The primary objective of the present study is to obtain the distributions of the amplitude and frequency of a temperature fluc
Autor:
SANG JI KIM, YONGHEE KIM, SERGI HONG, CHUNG HO CHO, JAE-HYUK EOH, JONG BUM KIM, MYUNG HWAN WI, KWI SEOK HA, EUI KWANG KIM
Publikováno v:
Nuclear Technology; Apr2010, Vol. 170 Issue 1, p148-158, 11p, 4 Diagrams, 5 Charts, 4 Graphs