Zobrazeno 1 - 10
of 28
pro vyhledávání: '"Duck Young Ku"'
The effect of Li2TiO3 pebbles on the mechanical properties of ARAA under breeding blanket conditions
Publikováno v:
Nuclear Materials and Energy, Vol 39, Iss , Pp 101658- (2024)
The breeding blanket serves as a critical element for achieving a self-sustaining tritium cycle and generating sufficient energy in fusion reactors. This study focuses on candidate materials of the helium-cooled solid breeder blanket designed for a d
Externí odkaz:
https://doaj.org/article/cf4b960a761c4bcb886d91f9794dc2d5
Publikováno v:
SSRN Electronic Journal.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::23575cac69ca2a5f1321c7085c2a91aa
https://doi.org/10.2139/ssrn.4109957
https://doi.org/10.2139/ssrn.4109957
Publikováno v:
Fusion Engineering and Design. 146:950-954
In order to verify the performance and safety of the solid-type breeding blanket concept, the thermal conductivity of the pebble bed is required as an essential parameter for design and analysis of the blanket. The hot wire, hot disk, guarded hot pla
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1afd1c3ec593738ffaf56806e30f5dc3
https://doi.org/10.1016/j.fusengdes.2019.01.122
https://doi.org/10.1016/j.fusengdes.2019.01.122
Autor:
Ji-Hyun Choi, Soon Chang Park, Hyung Gon Jin, Suk Kwon Kim, Dong Won Lee, Young-Bum Chun, Dong Jun Kim, Chang Shuk Kim, Seungyon Cho, Eo Hwak Lee, Kihak Im, Jae Sung Yoon, Cheol Woo Lee, Mu-Young Ahn, Seong Dae Park, Yi-Hyun Park, Duck Young Ku, Young-Min Lee
Publikováno v:
Fusion Engineering and Design. 136:190-198
Korea has own programs toward DEMO and fusion reactors that will require further improved DEMO blanket and energy utilization systems. Primary goals of DEMO blanket development in Korea are to develop and verify the integrated blanket design tools; t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9f655a9534ea37d1ccb93ea90bafd968
https://doi.org/10.1016/j.fusengdes.2018.01.050
https://doi.org/10.1016/j.fusengdes.2018.01.050
Autor:
Young-Min Lee, Chang-Shuk Kim, Seong Pyo Hong, Duck Young Ku, Bo Sun Kang, Mu-Young Ahn, Seungyon Cho
Publikováno v:
Fusion Engineering and Design. 136:717-721
The design of diagnostics system for the Helium Cooled Ceramic Reflector (HCCR) Test Blanket System (TBS) has now progressed from generic approaches to the conceptual design integration phases. It is proposed to monitor the temperature, strain, magne
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7c0e72c45f2bad2d778b39ec63852e62
https://doi.org/10.1016/j.fusengdes.2018.03.066
https://doi.org/10.1016/j.fusengdes.2018.03.066
Autor:
Soon Chang Park, Seungyon Cho, Jong-Il Kim, Eo Hwak Lee, Mu-Young Ahn, Bum Seok Kim, Young-Bum Chun, Seong Dae Park, Hyeong-Yeon Lee, Hyung Gon Jin, Dong Won Lee, Chang-Shuk Kim, Jae Sung Yoon, Young-Min Lee, Hyoseong Gwon, Suk-Kwon Kim, Duck Young Ku, Seok-Kwon Son, Cheol Woo Lee, Chang Wook Shin, Yi-Hyun Park, Sunghwan Yun
Publikováno v:
Fusion Engineering and Design. 171:112553
Development of the Helium Cooled Ceramic Reflector (HCCR) breeding blanket is underway according to the development strategy of core technology for K-DEMO under the fusion energy development roadmap in Korea. The main goals are to validate integrated
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7cdb822577ff2fde79ef597bf4157e89
https://doi.org/10.1016/j.fusengdes.2021.112553
https://doi.org/10.1016/j.fusengdes.2021.112553
Publikováno v:
Fusion Engineering and Design. 124:995-998
Since the stress due to the thermal load on breeding blanket structure is one of the main design driver, the thermal conductivity is necessary input data for thermal-structural and thermo-hydraulic analyses performed in order to understand the heat t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::84b41381fdc8519774ba98823ca3f281
https://doi.org/10.1016/j.fusengdes.2017.05.090
https://doi.org/10.1016/j.fusengdes.2017.05.090
Autor:
Young-Min Lee, Dong Won Lee, Hyung Gon Jin, Duck Young Ku, Jae Sung Yoon, Kyu In Shin, Seungyon Cho, Eo Hwak Lee, Seong Dae Park, Jai Hak Park, Suk-Kwon Kim
Publikováno v:
Fusion Engineering and Design. :554-560
Using a conceptual design of the Korean helium cooled ceramic reflector (HCCR) test blanket module (TBM) including the TBM-shield for testing in ITER, a structural analysis with electro-magnetic (EM) loads is performed. From a previous analysis of th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f6d05b764e065b810ba8a0ee5a2683ad
https://doi.org/10.1016/j.fusengdes.2016.02.056
https://doi.org/10.1016/j.fusengdes.2016.02.056
Publikováno v:
Fusion Engineering and Design. :1825-1828
Korean Helium Cooled Ceramic Reflector (HCCR) Test Blanket Module (TBM) will be installed at the #18 equatorial port of the Vaccum Vessel in order to test the feasibility of the breeding blanket performance for forthcoming fusion power plant in the I
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f4adc409dcbc60dbdbcd393e4bba90fa
https://doi.org/10.1016/j.fusengdes.2015.06.128
https://doi.org/10.1016/j.fusengdes.2015.06.128
Autor:
Dong Won Lee, Yi-Hyun Park, Seungyon Cho, Young-Min Lee, Hyung Gon Jin, Chang-Shuk Kim, Mu-Young Ahn, Duck Young Ku
Publikováno v:
Fusion Engineering and Design. 89:1289-1293
Korea has decided to test Helium Cooled Ceramic Reflector (HCCR) Test Blanket Module (TBM) in ITER and design of the TBM with its ancillary systems, i.e. Test Blanket System (TBS), is under progress. Since the TBM is operated at elevated temperature
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f18a60918a0e8b3547364b70030762b7
https://doi.org/10.1016/j.fusengdes.2014.03.021
https://doi.org/10.1016/j.fusengdes.2014.03.021