Zobrazeno 1 - 10
of 102
pro vyhledávání: '"HWAN-SEO PARK"'
Autor:
Jung-Hoon Choi, Byeonggwan Lee, Ki-Rak Lee, Hyun Woo Kang, Hyeon Jin Eom, Seong-Sik Shin, Ga-Yeong Kim, Geun-Il Park, Hwan-Seo Park
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 12, Pp 4441-4448 (2022)
The electrochemical oxidation process has been widely studied in the field of wastewater treatment for the decomposition of organic materials through oxidation using ⋅OH generated on the anode. Pt anode electrodes with high durability and long-term
Externí odkaz:
https://doaj.org/article/ebcc5a31360148b2be8d2a311be808e6
Autor:
Byeonggwan Lee, Jung-Hoon Choi, Ki Rak Lee, Hyun Woo Kang, Hyeon Jin Eom, Kyuchul Shin, Hwan-Seo Park
Publikováno v:
Heliyon, Vol 9, Iss 7, Pp e18406- (2023)
When disposing of spent fuel, nuclides such as Cs-137 and Sr-90, which generate short-term decay heat, must be removed from the spent nuclear fuel for efficient storage facility utilization. The Korea Atomic Energy Research Institute (KAERI) has been
Externí odkaz:
https://doaj.org/article/281845e767fd43b1a764da6c851f8a88
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 4, Pp 1206-1212 (2022)
Cold-crucible induction melting (CCIM) technology has been intensively studied as an advanced vitrification process for the immobilization of highly radioactive waste. This technology uses high-frequency induction to melt a glass matrix and waste, wh
Externí odkaz:
https://doaj.org/article/1703430b64db4c5db8d4582679766b4d
Autor:
Jung-Hoon Choi, Byeonggwan Lee, Ki-Rak Lee, Hyun Woo Kang, Hyeon Jin Eom, Seong-Sik Shin, Ga-Yeong Kim, Hwan-Seo Park
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2022 (2022)
To reduce the environmental burden caused by the disposal of spent nuclear fuel, waste burden minimization technology is currently being developed at the Korea Atomic Energy Research Institute. The technology includes a nuclide management process tha
Externí odkaz:
https://doaj.org/article/92234780b7e34728b0bb62c5de512ee4
Publikováno v:
Nuclear Engineering and Technology, Vol 45, Iss 5, Pp 675-682 (2013)
The sequential separation process, composed of an oxygen sparging process for separating lanthanides and a zone freezing process for separating Group I and II fission products, was evaluated and tested with a surrogate eutectic waste salt generated f
Externí odkaz:
https://doaj.org/article/fc957d7a6ee24898851af4934649edae
Autor:
Seonyoung Jo, Hyeonmin Lee, Tae Hyeon Kim, Kune-Woo Lee, Hwan-seo Park, Hee Reyoung Kim, Taek Seung Lee
Publikováno v:
ACS Applied Polymer Materials. 5:2472-2480
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::acbeb30fc708f32cc8c7d4ce48bccf32
https://doi.org/10.1021/acsapm.2c02145
https://doi.org/10.1021/acsapm.2c02145
Publikováno v:
Nuclear Engineering and Technology. 54:1206-1212
Cold-crucible induction melting (CCIM) technology has been intensively studied as an advanced vitrification process for the immobilization of highly radioactive waste. This technology uses high-frequency induction to melt a glass matrix and waste, wh
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1efeb77db64c3ceb7d5645cdf4acb93a
https://doi.org/10.1016/j.net.2021.09.041
https://doi.org/10.1016/j.net.2021.09.041
Autor:
Hyun Woo Kang, Hyeon Jin Eom, Hwan-Seo Park, Jung-Hoon Choi, Byeonggwan Lee, Ki Rak Lee, Kyuchul Shin
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 331:275-281
Sr-90 is utilized as a raw material in various fields such as nuclear batteries, medical applications, and industrial use as a beta particle source. Therefore, high-purity Sr-90 is required to increase the thermal efficiency of nuclear battery operat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::56f359398a5577dd9702f3a8b1420063
https://doi.org/10.1007/s10967-021-08082-3
https://doi.org/10.1007/s10967-021-08082-3
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 328:65-70
The diameter of the cylindrical waste form must be optimized through the estimated centerline temperature for thermally stable disposal. Salt wastes generated from pyrochemical processes were dechlorinated and vitrified using a universal silica alumi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3cb0b61725968918432618e468efc80d
https://doi.org/10.1007/s10967-020-07542-6
https://doi.org/10.1007/s10967-020-07542-6
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 326:1351-1359
An iodine immobilization matrix, the AgI–Ag2O–TeO2 glass system, was developed. The effects of different additives, i.e., Bi2O3, Al2O3, and PbO, on performance were investigated. In an ambient atmosphere and at 800 °C, the melting of the glass p
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::995be7e1b7d42c5f73abbef8e3bc831a
https://doi.org/10.1007/s10967-020-07421-0
https://doi.org/10.1007/s10967-020-07421-0