Zobrazeno 1 - 10
of 83
pro vyhledávání: '"YUNG-ZUN CHO"'
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2020 (2020)
We are developing a practical-scale mechanical decladder that can slit nuclear spent fuel rod-cuts (hulls + pellets) on the order of several tens of kgf of heavy metal/batch to supply UO2 pellets to a voloxidation process. The mechanical decladder is
Externí odkaz:
https://doaj.org/article/bfe8fc5715ce4436905ffb2a1c863e55
Autor:
Young-Hwan Kim, Yung-Zun Cho
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2020 (2020)
We have developed a practical-scale dry disassembling process to dismantle PWR (Pressurized Water Reactor) spent nuclear fuel assembly in the order of several tens of kilograms of heavy metal/batch to supply rod-cuts (cladding tube and UO2 pellets) f
Externí odkaz:
https://doaj.org/article/ce52f78109564199975c27b6ed3e2b51
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2019 (2019)
A practical scale mechanical decladder that can slit spent nuclear fuel rod-cuts (hulls + pellets) of several tens of kg HM/batch is being developed to supply UO2 pellets to a voloxidation process. The mechanical decladder is an apparatus for separat
Externí odkaz:
https://doaj.org/article/eb72c2cd0b8c4e528db12b4b6932cbf3
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 330:695-705
The management of radioactive carbon (C-14) from spent nuclear fuel (SNF) in a voloxidation process is vital to prevent radioactive contamination of the environment. Thus, a double alkali method was applied to absorb the gaseous phase of C-14 (CO2) a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::867ab70ff1b3619a228a261a031c0ae2
https://doi.org/10.1007/s10967-021-07972-w
https://doi.org/10.1007/s10967-021-07972-w
Publikováno v:
Journal of Environmental Chemical Engineering. 11:109743
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::76429fca3e8e33b374a52abc519d6ba6
https://doi.org/10.1016/j.jece.2023.109743
https://doi.org/10.1016/j.jece.2023.109743
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2017 (2017)
A voloxidizer with a double reactor capable of processing several tens of kilograms of HM/batch of nuclear spent fuel has been developed for the decladding and voloxidation of rod-cuts into hulls and pellets through the conversion of UO2 pellets to U
Externí odkaz:
https://doaj.org/article/6c99baf41e9c4b24a52c0f44b1d3bcd1
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:
Yung-Zun Cho, Young-Hwan Kim
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2020 (2020)
We have developed a practical-scale dry disassembling process to dismantle PWR (Pressurized Water Reactor) spent nuclear fuel assembly in the order of several tens of kilograms of heavy metal/batch to supply rod-cuts (cladding tube and UO2 pellets) f
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::cea98bc29db83c174d32506a13629db4
https://doi.org/10.1155/2020/8868444
https://doi.org/10.1155/2020/8868444
Autor:
Sang-Chae Jeon, Jae-Won Lee, Ju-Ho Lee, Sang-Jun Kang, Kwang-Yun Lee, Yung-Zun Cho, Do-Hee Ahn, Kee-Chan Song
Publikováno v:
Advances in Materials Science and Engineering, Vol 2015 (2015)
In the pyroprocess integrated inactive demonstration (PRIDE) facility at the Korea Atomic Energy Research Institute (KAERI), UO2 porous pellets were fabricated as a feed material for electrolytic reduction on an engineering scale of 30 kg-U/batch. To
Externí odkaz:
https://doaj.org/article/d6dff99d315d41b5bb65a996a53144a7
Autor:
Hwan-Seo Park, Ki-Rak Lee, Seung Youb Han, Jung-Hoon Choi, Yung-Zun Cho, Geun-Il Park, Min Ku Jeon, In-Tae Kim
Publikováno v:
Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT). 17:279-298
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bba0894da8769da967a2f907c3b6ef09
https://doi.org/10.7733/jnfcwt.2019.17.3.279
https://doi.org/10.7733/jnfcwt.2019.17.3.279