Zobrazeno 1 - 10
of 11
pro vyhledávání: '"Seok-Kyu Chang"'
Publikováno v:
Nuclear Engineering and Technology, Vol 48, Iss 2, Pp 376-385 (2016)
A hexagonally arrayed 37-pin wire-wrapped rod bundle has been chosen to provide the experimental data of the pressure loss and flow rate in subchannels for validating subchannel analysis codes for the sodium-cooled fast reactor core thermal/hydraulic
Externí odkaz:
https://doaj.org/article/72473978cf6a41639c161ba1734caeb7
Autor:
Dong-Jin Euh, Sun Rock Choi, Seok-Kyu Chang, Won Sik Yang, Hae Seob Choi, Hyungmo Kim, Hyeong-Yeon Lee
Publikováno v:
Annals of Nuclear Energy. 166:108810
Flow mixing between adjacent subchannels within a wire-wrapped hexagonal fuel rod bundle affects radial heat transfer and determines the maximum cladding temperature, which is a key parameter to ensure the fuel safety margin in a sodium-cooled fast r
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a541d05f50af24beddc82e4eca319b53
https://doi.org/10.1016/j.anucene.2021.108810
https://doi.org/10.1016/j.anucene.2021.108810
Autor:
Yung Joo Ko, Hyeong-Yeon Lee, Hae Seob Choi, Seok-Kyu Chang, Hyungmo Kim, Sun Rock Choi, Seok Hoon Kim, Dong-Jin Euh
Publikováno v:
Annals of Nuclear Energy. 106:160-169
Hydrodynamic experiments were performed to characterize pressure drop and flow distribution in the subchannels of KAERI’s fuel bundle configuration. A 61-pin wire wrapped rod bundle was chosen as a test assembly considering the hydrodynamic similar
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::65aebe1ed0456f7472f96eae3d0c8497
https://doi.org/10.1016/j.anucene.2017.03.024
https://doi.org/10.1016/j.anucene.2017.03.024
Autor:
Hae Seob Choi, Dong-Won Lee, Hwang Bae, Sun Rock Choi, Hyeong-Yeon Lee, Hyungmo Kim, Yung Joo Ko, Seok-Kyu Chang, Dong-Jin Euh
Publikováno v:
Annals of Nuclear Energy. 87:541-546
Flow mixing characteristics inside a wire-wrapped 37-pin bundle were measured using a wire-mesh sensing system. The subchannel flow mixing within a sodium-cooled fast reactor (SFR) core subassembly is an important phenomenon to predict temperature di
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1f4356d6360f60e4e4fe3ca7392f748c
https://doi.org/10.1016/j.anucene.2015.09.022
https://doi.org/10.1016/j.anucene.2015.09.022
Experimental Methodology Development for SFR Subchannel Analysis Code Validation with 37-Rods Bundle
Autor:
Seok Jin Kim, Hae-Seob Choi, Hwang Bae, Hyungmo Kim, Sun-Rock Choi, Dong-Jin Euh, Seok-Kyu Chang, Hyung-Yeon Lee
Publikováno v:
Journal of Fluid Machinery. 17:89-94
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f1755d115e27f3a7310c78bb37bbb688
https://doi.org/10.5293/kfma.2014.17.6.089
https://doi.org/10.5293/kfma.2014.17.6.089
Turbulent mixing in a rod bundle with vaned spacer grids: OECD/NEA–KAERI CFD benchmark exercise test
Publikováno v:
Nuclear Engineering and Design. 279:19-36
An experimental study titled the 2nd International Benchmark Exercise (IBE-2) has been conducted to provide high-precision data of detailed turbulent flow mixing in a rod bundle for validating the CFD codes being used widely in the nuclear power indu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2ac04d550e2215dde89e2d74e84f5a45
https://doi.org/10.1016/j.nucengdes.2014.05.013
https://doi.org/10.1016/j.nucengdes.2014.05.013
Publikováno v:
Heat Transfer Engineering. 29:695-703
The lateral flow structures in a subchannel geometry were carefully examined in an enlarged 5 × 5 rod bundle array by using a two-color LDA system. The detailed measurement data of lateral velocities in subchannels have been obtained as fabricating
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6f55bed1dc440c8f3d17d2d37117936a
https://doi.org/10.1080/01457630801981564
https://doi.org/10.1080/01457630801981564
Publikováno v:
Nuclear Engineering and Design. 238:600-609
Detailed turbulent flow profiles have been measured on a square sub-channel geometry with typical mixing devices. For a fine examination of the lateral flow structure on a sub-channel geometry with 2D LDA, a 5 × 5 rod bundle array was fabricated as
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2af59b7100377eb7a5eee914a1148f71
https://doi.org/10.1016/j.nucengdes.2007.02.037
https://doi.org/10.1016/j.nucengdes.2007.02.037
Autor:
Seok-Kyu Chang, Chang-Hwan Chung, Choon-Kyung Park, Nam-Hyun Choi, Sung-Jae Yi, Moon-Ki Chung, Hyun-Sik Park
Publikováno v:
International Journal of Multiphase Flow. 33:1222-1236
An experimental study was performed on a two-phase critical flow with a non-condensable gas at high pressure conditions. Experimental data for the critical flow rates were generated by using sharp-edged stainless steel pipes with an inner diameter of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3f8246fcc431497aa10948d412c20557
https://doi.org/10.1016/j.ijmultiphaseflow.2007.05.008
https://doi.org/10.1016/j.ijmultiphaseflow.2007.05.008
Publikováno v:
Nuclear Engineering and Design. 200:407-419
A static analysis, finite-element (FE) model was developed to simulate out-reactor fuel–string strength tests with use of the well-known, structural analysis computer code ABAQUS. The FE model takes into account the deflection of fuel elements, and
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::97667a22bba9fde028f43c4b208d5857
https://doi.org/10.1016/s0029-5493(00)00248-x
https://doi.org/10.1016/s0029-5493(00)00248-x