Zobrazeno 1 - 10
of 24
pro vyhledávání: '"Youko Takahatake"'
Autor:
Toshihiro IWAMOTO, Madoka SAITO, Youko TAKAHATAKE, Sou WATANABE, Masayuki WATANABE, Atsuki NARUSE, Takehiko TSUKAHARA
Publikováno v:
Mechanical Engineering Journal, Vol 11, Iss 2, Pp 23-00444-23-00444 (2024)
Nuclear fuel fabrication process has generated a large amount of wastes contaminated with enriched uranium, and those have been accumulated for long time in Japan. These waste hasn’t treated, because there is no protocol to treat and dispose these.
Externí odkaz:
https://doaj.org/article/fa720698ade04ff493e06977d54b226e
Autor:
Sou WATANABE, Youko TAKAHATAKE, Kenta HASEGAWA, Ichiro GOTO, Yasunori MIYAZAKI, Masayuki WATANABE, Yuichi SANO, Masayuki TAKEUCHI
Publikováno v:
Mechanical Engineering Journal, Vol 11, Iss 2, Pp 23-00461-23-00461 (2024)
Japan Atomic Energy Agency is developing extraction chromatography technology to recover MA(III) from spent nuclear fuel. Developments in the extraction chromatography system especially focusing on safety and stable operation are required for practic
Externí odkaz:
https://doaj.org/article/587ff6c6e94d40bea808007d95852c37
Autor:
Yuri YAMAMOTO, Kazuki MINOWA, Youko TAKAHATAKE, Sou WATANABE, Masahiro NAKAMURA, Haruaki MATSUURA
Publikováno v:
Electrochemistry, Vol 92, Iss 4, Pp 043019-043019 (2024)
In the pyro-reprocessing of spent nuclear fuel, salt bath is normally used in several times, but at final moment, spent salt containing small amount of chloride nuclear fuel material is generated. In terms of managing nuclear fuel materials, it is de
Externí odkaz:
https://doaj.org/article/3a8cfc1032754f1bb24809329a82b3a3
Publikováno v:
Applied Radiation and Isotopes. 196:110783
Publikováno v:
Journal of Nuclear Science and Technology. 58:493-506
A modeling calculation methodology for estimating the radionuclide composition in the wastes generated at the Fukushima Daiichi nuclear power station has been upgraded by introducing an approach us...
Autor:
Youko Takahatake1,2 takahatake.yoko@jaea.go.jp, Atsuhiro Shibata1 shibata.atsuhiro@jaea.go.jp, Kazunori Nomura1 nomura.kazunori@jaea.go.jp, Tsutomu Sato3 tomsato@eng.hokudai.ac.jp
Publikováno v:
Minerals (2075-163X). Dec2017, Vol. 7 Issue 12, p247. 14p.
Purification of Spent Salt from Pyroprocess Experiments by Precipitation and Distillation Techniques
Autor:
Jun-ya Ibe, Mao Mitani, Megumi Aso, Youko Takahatake, Sou Watanabe, Masayuki Watanabe, Haruaki Matsuura
Publikováno v:
SSRN Electronic Journal.
Publikováno v:
Journal of Nuclear Science and Technology. 56:881-890
A calculation methodology for estimating the radionuclide composition in the wastes generated at the Fukushima Daiichi nuclear power station has been developed by constructing a skeleton overview o...
Publikováno v:
Journal of Nuclear Materials. 556:153170
The long-time experimental activities on pyroprocessing have generated waste eutectic salts contaminated with nuclear materials. Composition and degree of contamination of waste eutectic salts depended on their history. After reprocessing tests, wast
Publikováno v:
Minerals, Vol 7, Iss 12, p 247 (2017)
Minerals; Volume 7; Issue 12; Pages: 247
Minerals; Volume 7; Issue 12; Pages: 247
Radioactive contaminated water has been generated at the Fukushima Daiichi Nuclear Power station (F1NPS). Hydrous sodium titanate (SrTreat (R)) is able to remove radioactive Strontium (Sr) from this water. Knowing the amount of radioactive nuclides i