Zobrazeno 1 - 10
of 33
pro vyhledávání: '"Young-Dug Bae"'
Publikováno v:
Fusion Engineering and Design. 88:276-281
In the ITER tokamak, the toroidal magnetic field (TF) ripple is estimated with TF coils only, with the installation of ferromagnetic inserts (FIs), and with test blanket modules (TBMs) by using a 2-D code for easy and fast calculation. We assessed th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::08f721d5d712544ddec632b907763dde
https://doi.org/10.1016/j.fusengdes.2013.02.121
https://doi.org/10.1016/j.fusengdes.2013.02.121
Autor:
Jeong-Yong Park, Suk-Kwon Kim, Yong-Hwan Jeong, Hyun-Kyu Jung, Young-Dug Bae, Dong Won Lee, Yang-Il Jung
Publikováno v:
Fusion Engineering and Design. 86:1766-1770
The main topic of an ITER blanket first wall procurement is to qualify whether each party has the key technology needed for the fabrication and joining of first wall components. A semi-prototype qualification project will be released requiring that t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::53111c453bb086ab34edf7db7793c637
https://doi.org/10.1016/j.fusengdes.2011.02.087
https://doi.org/10.1016/j.fusengdes.2011.02.087
Publikováno v:
Journal of Nuclear Materials. 417:63-66
In order for a Korean Helium Cooled Molten Lithium (HCML) Test Blanket Module (TBM) to be tested in the International Thermonuclear Experimental Reactor (ITER), fabrication method for the TBM FW such as Hot Isostatic Pressing (HIP, 1050 °C, 100 MPa,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a41eb6cfc27de03a986a5f8cb53f4149
https://doi.org/10.1016/j.jnucmat.2010.12.166
https://doi.org/10.1016/j.jnucmat.2010.12.166
Publikováno v:
Fusion Engineering and Design. 86:2212-2215
In order to develop a Li-based test blank module (TBM) in the International Thermonuclear Experimental Reactor (ITER), an Experimental Loop for Liquid breeder (ELLI) was constructed and its test operation was completed. The ELLI consists of a sump ta
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a536515bcf6b7b170bd18e88d4abffd9
https://doi.org/10.1016/j.fusengdes.2011.04.036
https://doi.org/10.1016/j.fusengdes.2011.04.036
Autor:
Jeong Yong Park, Yong Hwan Jeong, Seungyon Cho, Young-Dug Bae, Suk Kwon Kim, Yang-Il Jung, Dong Won Lee
Publikováno v:
Fusion Engineering and Design. 86:1697-1701
Korea has proposed and designed a helium cooled molten lithium (HCML) test blanket module (TBM) to be tested in the ITER, in which Ferrite Martensite steel (FMS) and Be were used as the structural and armor materials of the first wall (FW), respectiv
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::eb97c383bc834d54a2d431ec08c64e90
https://doi.org/10.1016/j.fusengdes.2010.11.014
https://doi.org/10.1016/j.fusengdes.2010.11.014
Publikováno v:
Fusion Science and Technology. 60:139-143
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::429a6818cf8012762786f52510d6c91e
https://doi.org/10.13182/fst11-a12341
https://doi.org/10.13182/fst11-a12341
Autor:
Young-Dug Bae, Jeong-Yong Park, Dong Won Lee, Byoung-Yoon Kim, Jae-Sung Yoon, Yang-Il Jung, Yong-Hwan Jeong, Hyun-Kyu Jung, Suk-Kwon Kim
Publikováno v:
Fusion Science and Technology. 60:161-164
The Korean standard mockups with beryllium tile were fabricated to perform the high heat flux test for the qualification test of ITER blanket first wall. These mockups include the 80 mm × 80 mm ber...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5322e0effe3c584eb023c159f0dd8753
https://doi.org/10.13182/fst11-a12345
https://doi.org/10.13182/fst11-a12345
Autor:
Suk Kwon Kim, Yang-Il Jung, Yong Hwan Jeong, Dong Won Lee, Jeong Yong Park, Byung Yoon Kim, Young-Dug Bae
Publikováno v:
Fusion Science and Technology. 60:165-169
For the second qualification of the blanket First Wall (FW) procurement of the International Thermonuclear Experimental Reactor (ITER), a semi-prototype of the FW has been designed with increased local surface heat flux up to 5 MW/m2. In order to inv
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3b6e2c56d446c942840d7a0165aabd3b
https://doi.org/10.13182/fst11-a12346
https://doi.org/10.13182/fst11-a12346
Autor:
Dong Won Lee, Jeong Yong Park, Byung-Kwon Choi, Byoung-Yoon Kim, Young Dug Bae, Suk Kwon Kim, Hyun Kyu Jung, Yong Hwan Jeong
Publikováno v:
Nuclear Engineering and Technology. 42:662-669
To develop the manufacturing methods for the blanket first wall (FW) of the International Thermonuclear Experimental Reactor (ITER) and to verify the integrity of the joint, Be/Cu mockups were fabricated and tested at the KoHLT-1 (Korea Heat Load Tes
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::eb2017cb360e164683899da8b61acae5
https://doi.org/10.5516/net.2010.42.6.662
https://doi.org/10.5516/net.2010.42.6.662
Autor:
Sung Deok Hong, Nam Il Tak, Chan Su Kim, Dong Won Lee, In Cheol Bang, Suk Kwon Kim, Young Dug Bae, Bong Guen Hong
Publikováno v:
Fusion Engineering and Design. 85:2160-2164
In considering the requirements for a DEMO-relevant blanket concept, Korea (KO) has proposed a Helium Cooled Molten Lithium (HCML) Test Blanket Module (TBM) for testing in the International Thermonuclear Experimental Reactor (ITER). The performance a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2b98dfcbefc18adeaefe03154ea20e20
https://doi.org/10.1016/j.fusengdes.2010.08.024
https://doi.org/10.1016/j.fusengdes.2010.08.024