팔로우
Tae-Hyun Chun
Tae-Hyun Chun
kaeri.re.kr의 이메일 확인됨
제목
인용
인용
연도
Thermal hydraulic performance assessment of dual-cooled annular nuclear fuel for OPR-1000
CH Shin, TH Chun, DS Oh, WK In
Nuclear Engineering and Design 243, 291-300, 2012
762012
Effect of change in surface condition induced by oxidation on transient pool boiling heat transfer of vertical stainless steel and copper rodlets
CY Lee, TH Chun, WK In
International journal of heat and mass transfer 79, 397-407, 2014
692014
High-fidelity light water reactor analysis with the numerical nuclear reactor
DP Weber, T Sofu, WS Yang, TJ Downar, JW Thomas, Z Zhong, JY Cho, ...
Nuclear Science and Engineering 155 (3), 395-408, 2007
692007
A pressure drop model for spacer grids with and without flow mixing vanes
TH Chun, DS Oh
Journal of Nuclear Science and Technology 35 (7), 508-510, 1998
681998
Evaluation of a dual-cooled annular fuel heat split and temperature distribution
YS Yang, CH Shin, TH Chun, KW Song
Journal of nuclear science and technology 46 (8), 836-845, 2009
642009
Flow analysis for optimum design of mixing vane in a PWR fuel assembly
WK In, DS Oh, TH Chun
Nuclear Engineering and Technology 33 (3), 327-338, 2001
572001
Grid with nozzle-type coolant deflecting channels for use in nuclear reactor fuel assemblies
HS Kang, KN Song, KH Yoon, YH Jung, TH Chun, DS Oh, WK In, JG Bang
US Patent 6,130,927, 2000
532000
Numerical computation of heat transfer enhancement of a PWR rod bundle with mixing vane spacers
WK In, TH Chun, CH Shin, DS Oh
Nuclear Technology 161 (1), 69-79, 2008
432008
Fuel assembly spacer grid with swirl deflectors and hydraulic pressure springs
TH Chun, DS Oh, WK In, KN Song, HS Kang, KH Yoon, DH Kim, JG Bang, ...
US Patent 6,236,702, 2001
372001
High burnup fuel technology in Korea
KW Song, YH Jeong, KS Kim, JG Bang, TH Chun, HK Kim, KN Song
Nuclear Engineering and Technology 40 (1), 21, 2008
342008
Spacer grid for nuclear reactor fuel assemblies with grid springs maintaining conformal contact with fuel rods and enlarged elastic range
KH Yoon, HS Kang, HK Kim, KN Song, YH Jung, TH Chun, DS Oh, WK In, ...
US Patent 6,707,872, 2004
302004
An integral equation model for critical heat flux at subcooled and low quality flow boiling
TH Chun, WP Baek, SH Chang
Nuclear engineering and design 199 (1-2), 13-29, 2000
292000
Critical heat flux of oxidized zircaloy surface in saturated water pool boiling
CY Lee, TH Chun, W Kee In
Journal of Nuclear Science and Technology 52 (4), 596-606, 2015
272015
Spacer grid with hybrid flow-mixing device for nuclear fuel assembly
T Chun, D Oh, W In, K Song, H Kim, H Kang, K Yoon, Y Jung
US Patent 6,845,138, 2005
272005
Spacer grid with multi-springs and dimple vanes for nuclear fuel assemblies
K Yoon, H Kang, K Song, YH Jung, T Chun, D Oh, W In
US Patent 6,278,759, 2001
272001
Conceptual design of OPR-1000 compatible annular fuel assembly
S Yong, M Kang, H Chang, H Tae, G Je, WS Kun
262007
Empirical and computational pressure drop correlations for pressurized water reactor fuel spacer grids
WK In, DS Oh, TH Chun
Nuclear technology 139 (1), 72-79, 2002
262002
Simulation of turbulent flow in rod bundles using eddy viscosity models and Reynolds stress model
WK In, DS Oh, TH Chun
242003
Nuclear fuel spacer grid with dipper vanes
HS Kang, KH Yoon, HK Kim, KN Song, YH Jung, TH Chun, DS Oh, WK In
US Patent 6,421,407, 2002
242002
Spacer grid with H-spring for fuel rods for use in nuclear reactor fuel assemblies
KH Yoon, HS Kang, HK Kim, KN Song, YH Jung, TH Chun, DS Oh, WK In
US Patent 6,167,105, 2000
242000
현재 시스템이 작동되지 않습니다. 나중에 다시 시도해 주세요.
학술자료 1–20