Zobrazeno 1 - 10
of 19
pro vyhledávání: '"Dong Hyun Heo"'
Autor:
Sung-Wook Kim, Jong Kwang Lee, Dongseok Ryu, Min Ku Jeon, Sun-Seok Hong, Dong Hyun Heo, Eun-Young Choi
Publikováno v:
Nuclear Engineering and Technology, Vol 50, Iss 7, Pp 1184-1189 (2018)
Pyroprocessing uses various molten salts during electrochemical unit processes. Reaction products after the electrochemical processes must contain a significant amount of residual salts to be separated. Vacuum distillation is a common method to separ
Externí odkaz:
https://doaj.org/article/d6cc3f8a96e44cdea80ef509aef65b8f
Autor:
Sung-Wook Kim, Dong Hyun Heo, Sang Kwon Lee, Min Ku Jeon, Wooshin Park, Jin-Mok Hur, Sun-Seok Hong, Seung-Chul Oh, Eun-Young Choi
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 7, Pp 1451-1456 (2017)
Finding technical issues associated with equipment scale-up is an important subject for the investigation of pyroprocessing. In this respect, electrolytic reduction of 1 kg UO2, a unit process of pyroprocessing, was conducted using graphite as an ano
Externí odkaz:
https://doaj.org/article/72509ad4acec4890a69ef45359c9564c
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2017 (2017)
We demonstrated that the metallic product obtained after electrolytic reduction (also called oxide reduction (OR)) can be simply separated from a stainless steel wire mesh cathode basket only by using a salt drain. First, the OR run of a simulated ox
Externí odkaz:
https://doaj.org/article/0a21ead7a8ed40bdbea4660c988b7faf
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2017 (2017)
Quantitative analysis by in situ measurement of oxygen gas evolved from an anode was employed to monitor the progress of electrolytic reduction of simulated oxide fuel in a molten Li2O–LiCl salt. The electrolytic reduction of 0.6 kg of simulated ox
Externí odkaz:
https://doaj.org/article/7ff41793deb642da8b484e2c9778d5df
Autor:
Eun-Young Choi, Dong Hyun Heo
Publikováno v:
Journal of Nuclear Materials. 512:193-198
The reduction of zirconium oxide compounds by Li metal as a reductant in molten LiCl salt was investigated. This study explored the feasibility of treating damaged nuclear fuel debris, which mainly consists of (U,Zr)O2. The production of metallic Zr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7017488b397ca82b4be503ba15fac3ba
https://doi.org/10.1016/j.jnucmat.2018.10.015
https://doi.org/10.1016/j.jnucmat.2018.10.015
Autor:
Dongseok Ryu, Sun-Seok Hong, Eun-Young Choi, Jong Kwang Lee, Sung-Wook Kim, Dong Hyun Heo, Min Ku Jeon
Publikováno v:
Nuclear Engineering and Technology, Vol 50, Iss 7, Pp 1184-1189 (2018)
Pyroprocessing uses various molten salts during electrochemical unit processes. Reaction products after the electrochemical processes must contain a significant amount of residual salts to be separated. Vacuum distillation is a common method to separ
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::7338855169db4f2bc343de1c07e3f18e
https://doi.org/10.1016/j.net.2018.06.009
https://doi.org/10.1016/j.net.2018.06.009
Autor:
Sun-Seok Hong, Seung-Chul Oh, Wooshin Park, Eun-Young Choi, Sang-Kwon Lee, Sung-Wook Kim, Jin-Mok Hur, Min Ku Jeon, Dong Hyun Heo
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 7, Pp 1451-1456 (2017)
Finding technical issues associated with equipment scale-up is an important subject for the investigation of pyroprocessing. In this respect, electrolytic reduction of 1 kg UO 2 , a unit process of pyroprocessing, was conducted using graphite as an a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::14513231f609721cf8c8e6d6414af99c
https://doi.org/10.1016/j.net.2017.05.004
https://doi.org/10.1016/j.net.2017.05.004
Autor:
Sung-Wook Kim, Sang-Chae Jeon, Jin-Mok Hur, Dong Hyun Heo, Sun Seok Hong, Sang-Kwon Lee, Eun-Young Choi, Hyun Woo Kang, Min Ku Jeon, Jeong Lee
Publikováno v:
Journal of Nuclear Materials. 489:1-8
Ten electrolytic reduction or oxide reduction (OR) runs of a 0.6 kg scale-simulated oxide fuel in a Li 2 O-LiCl molten salt at 650 °C were conducted using metal anode shrouds. During this procedure, an anode shroud surrounds a platinum anode and dis
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::eefcc386745bcad1af2b422311313872
https://doi.org/10.1016/j.jnucmat.2017.03.035
https://doi.org/10.1016/j.jnucmat.2017.03.035
Autor:
Jeong Lee, Sang-Chae Jeon, Sung-Wook Kim, Jin-Mok Hur, Sang-Kwon Lee, Eun-Young Choi, Sung-Jai Lee, Min Ku Jeon, Hyun Woo Kang, Dong Hyun Heo
Publikováno v:
Journal of Nuclear Materials. 485:90-97
We present our findings that uranium (U) metal prepared by using the electrolytic reduction process for U oxide (UO 2 ) in a Li 2 O–LiCl salt can be reoxidized into UO 2 through the reaction between the U metal and Li 2 O in LiCl. Two salt types we
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e726032e67886bfedcbb9da0a2b4d149
https://doi.org/10.1016/j.jnucmat.2016.12.017
https://doi.org/10.1016/j.jnucmat.2016.12.017
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2017 (2017)
Quantitative analysis by in situ measurement of oxygen gas evolved from an anode was employed to monitor the progress of electrolytic reduction of simulated oxide fuel in a molten Li2O–LiCl salt. The electrolytic reduction of 0.6 kg of simulated ox
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::4ee62d78345d92b525a4e6a1b85f0786
https://doi.org/10.1155/2017/2748302
https://doi.org/10.1155/2017/2748302