Zobrazeno 1 - 10
of 11
pro vyhledávání: '"Akito Ipponsugi"'
Publikováno v:
Nuclear Materials and Energy, Vol 25, Iss , Pp 100777- (2020)
Solid tritium breeding materials are used in a high temperature condition for a long time in a fusion reactor blanket. It is expected that a certain amount of Li will be evaporated and the pebble structure will be changed. Understanding of Li mass tr
Externí odkaz:
https://doaj.org/article/9ef11b66d5364453964e630cb33d4277
Autor:
Ruichong Chen, Akito Ipponsugi, Ran Oyama, Jianqi Qi, Haomin Wang, Zhangyi Huang, Hao Guo, Tiecheng Lu, Wei Feng, Kazunari Katayama
Publikováno v:
International Journal of Applied Ceramic Technology.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::915c73a9d2aedcba65528e51c02ea3df
https://doi.org/10.1111/ijac.14392
https://doi.org/10.1111/ijac.14392
Publikováno v:
Fusion Engineering and Design. 187:113374
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b64aef32100d7c7ba5328a41229031e7
https://doi.org/10.1016/j.fusengdes.2022.113374
https://doi.org/10.1016/j.fusengdes.2022.113374
Autor:
Ruichong Chen, Kazunari Katayama, Jianqi Qi, Akito Ipponsugi, Ran Oyama, Hao Guo, Tiecheng Lu
The development of novel tritium breeding materials was urgently needed in order to continuously optimize the tritium breeding ratio (TBR) of thermonuclear fusion reactors. From this point of view, Li4TiO4-Li2TiO3 core-shell breeding materials with m
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::99c972e18a694b04ee823a9bcc1211b7
https://doi.org/10.21203/rs.3.rs-1183339/v1
https://doi.org/10.21203/rs.3.rs-1183339/v1
Autor:
Ruichong Chen, Kazunari Katayama, Akito Ipponsugi, Ran Oyama, Hao Guo, Jianqi Qi, Zhijun Liao, Tiecheng Lu
Publikováno v:
Nuclear Fusion. 62:076030
In order to efficiently grasp the tritium behavior in advanced core–shell breeding materials, this study adopts a route of injecting tritium out-of-pile to deal with the problems of fewer platforms, long periods, and high costs for traditional neut
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c4be34b081e5190707752767dbda928b
https://doi.org/10.1088/1741-4326/ac6434
https://doi.org/10.1088/1741-4326/ac6434
Publikováno v:
Fusion Engineering and Design. 170:112495
Solid tritium breeding materials are expected to be used in high-temperature conditions for a long time in a fusion DEMO reactor. Thus, it is important to understand how bred tritium releases from the long-term heated material under the environment a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=jairo_______::6a1e8d71f81dd5cf619e662ce73b499d
https://repo.qst.go.jp/records/84700
https://repo.qst.go.jp/records/84700
Publikováno v:
Fusion Engineering and Design. 170:112495
Solid tritium breeding materials are expected to be used in high-temperature conditions for a long time in a fusion DEMO reactor. Thus, it is important to understand how bred tritium releases from the long-term heated material under the environment a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::00d1c7180b28ab2b82a9208abd8925f3
https://doi.org/10.1016/j.fusengdes.2021.112495
https://doi.org/10.1016/j.fusengdes.2021.112495
Autor:
Kenji Tobita, Makoto Oya, Hirofumi Nakamura, Youji Someya, Ryoji Hiwatari, Yuji Hatano, Akito Ipponsugi, Kazunari Katayama, Takumi Chikada, Yoshiteru Sakamoto
Publikováno v:
Fusion Engineering and Design. 169:112576
The estimation of tritium permeation rate through the plasma facing wall into coolant is required to discuss tritium balance in a D-T fusion plant, to design tritium recovery system and to perform safety assessments. In this work, tritium permeation
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4c2f55517cad634cd246dc50d293abd0
https://doi.org/10.1016/j.fusengdes.2021.112576
https://doi.org/10.1016/j.fusengdes.2021.112576
Autor:
Katayama, Kazunari, Yoji, Someya, Chikada, Takumi, Kenji, Tobita, Hirofumi, Nakamura, Yuji, Hatano, Ryoji, Hiwatari, Yoshiteru, Sakamoto, Akito, Ipponsugi, Oya, Makoto
Publikováno v:
Fusion Engineering and Design. 169:112576
The estimation of tritium permeation rate through the plasma facing wall into coolant is required to discuss tritium balance in a D-T fusion plant, to design tritium recovery system and to perform safety assessments. In this work, tritium permeation
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=jairo_______::7a382207b2f662dc134ecc34577c989b
https://repo.qst.go.jp/records/84580
https://repo.qst.go.jp/records/84580
Publikováno v:
Nuclear Materials and Energy, Vol 25, Iss, Pp 100777-(2020)
Solid tritium breeding materials are used in a high temperature condition for a long time in a fusion reactor blanket. It is expected that a certain amount of Li will be evaporated and the pebble structure will be changed. Understanding of Li mass tr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::4e21712f51d223c10b3fa6eaf60a663c
https://doi.org/10.1016/j.nme.2020.100777
https://doi.org/10.1016/j.nme.2020.100777