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adsorption 
lattice defect sites of Prussian blue filled with coordination and crystallization water moleculesIshizaki, Manabu*; Akiba, Sae*; Otani, Asako*; Hoshi, Yuji*; Ono, Kenta*; Matsuba, Mayu*; Togashi, Takanari*; Kanaizuka, Katsuhiko*; Sakamoto, Masatomi*; Takahashi, Akira*; et al.
Dalton Transactions, 42(45), p.16049 - 16055, 2013/12
Times Cited Count：178 Percentile：99.58(Chemistry, Inorganic & Nuclear)We have revealed the fundamental mechanism of specific Cs adsorption into Prussian blue (PB) in order to develop high-performance PB-based Cs adsorbents in the wake of the Fukushima nuclear accident. We compared two types of PB nanoparticles with formulae of Fe
[Fe
(CN)
]3
xH
O (x = 10-15) (PB-1) and (NH)0.70Fe1.10[Fe(CN)]1.7HO (PB-2) with respect to the Cs adsorption ability. The synthesised PB-1, by a common stoichiometric aqueous reaction between 4Fe
and 3[Fe(CN)]
, showed much more efficient Cs adsorption ability than did the commercially available PB-2.
Yamanishi, Toshihiko; Hayashi, Takumi; Shu, Wataru; Kawamura, Yoshinori; Nakamura, Hirofumi; Iwai, Yasunori; Kobayashi, Kazuhiro; Isobe, Kanetsugu; Arita, Tadaaki; Hoshi, Shuichi; et al.
Fusion Engineering and Design, 83(10-12), p.1359 - 1363, 2008/12
Times Cited Count：4 Percentile：29.49(Nuclear Science & Technology)At TPL (Tritium Process Laboratory) of JAEA, ITER relevant tritium technologies have been studied. The design studies of Air Detritiation System have been carried out in JAEA as a contribution of Japan to ITER. For the tritium processing technologies, our efforts have been focused on the research of the tritium recovery system of ITER test blanket system. A ceramic proton conductor has been studied as an advanced blanket system. A series of fundamental studies on tritium safety technologies not only for ITER but also for fusion DEMO plants has also been carried out at TPL of JAEA. The main research activities in this field are the tritium behavior in a confinement and its barrier materials; monitoring; accountancy; detritiation and decontamination etc. In this paper, the results of above recent activities at TPL of JAEA are summarized from viewpoint of ITER relevant and future fusion DEMO reactors.
Yamanishi, Toshihiko; Yamada, Masayuki; Suzuki, Takumi; Shu, Wataru; Kawamura, Yoshinori; Nakamura, Hirofumi; Iwai, Yasunori; Kobayashi, Kazuhiro; Isobe, Kanetsugu; Hoshi, Shuichi; et al.
Fusion Science and Technology, 54(1), p.315 - 318, 2008/07
Times Cited Count：11 Percentile：59.16(Nuclear Science & Technology)The construction of the building and safety systems of the TPL was completed until 1985. The operations of the safety systems with tritium have been started from March 1988. The amount of tritium held at the TPL was 13 PBq at March 2007. The average tritium concentration in a stream from a stack of the TPL to environment was 6.0
10
Bq/cm
; and is 1/100 smaller than that of the regulation value for the concentration of HTO in the air in Japan. The safety operation results with tritium have thus been obtained. A set of failure data of several main components of the TPL was also obtained as the valuable data for fusion tritium facilities.
Hayashi, Takumi; Isobe, Kanetsugu; Kobayashi, Kazuhiro; Iwai, Yasunori; Kawamura, Yoshinori; Nakamura, Hirofumi; Shu, Wataru; Arita, Tadaaki; Hoshi, Shuichi; Suzuki, Takumi; et al.
Fusion Science and Technology, 52(3), p.651 - 658, 2007/10
Times Cited Count：2 Percentile：18.73(Nuclear Science & Technology)The design studies of Air Detirtiation System have been carried out in JAEA as a contribution of Japan to ITER. For the tritium processing technologies, our efforts have been focused on the R&D of the tritium recovery system of ITER test blanket, using mainly molecular sieve and/or electro-chemical pumping system. A series of fundamental studies on tritium safety technologies, such as tritium behavior in a confinement and its barrier materials, monitoring, accountancy, detritiation and decontamination etc., has been carried out as a major activity in JAEA for ITER and fusion demo reactors. In this paper, the above recent activities on tritium technologies at Tritium Process Lab. in JAEA are summarized for ITER and future fusion reactor.
Takeuchi, Masayuki; Kubota, Masahiro; Hoshi, Masayuki; Sakauchi, Nobuyuki; Nakajima, Yasuo; Uchiyama, Gunzo; Nojima, Yasuo*; Fujine, Sachio*
no journal, ,
no abstracts in English
Sano, Yuichi; Takeuchi, Masayuki; Hoshi, Masayuki; Sakauchi, Nobuyuki; Hirano, Hiroyasu; Uchiyama, Gunzo; Nojima, Yasuo*; Fujine, Sachio*
no journal, ,
no abstracts in English
Sano, Yuichi; Takeuchi, Masayuki; Hoshi, Masayuki; Sakauchi, Nobuyuki; Hirano, Hiroyasu; Uchiyama, Gunzo; Nojima, Yasuo*; Fujine, Sachio*
no journal, ,
no abstracts in English
Ambai, Hiromu; Sano, Yuichi; Takeuchi, Masayuki; Hoshi, Masayuki; Sakauchi, Nobuyuki; Aose, Shinichi; Ogino, Hideki
no journal, ,
no abstracts in English
Ambai, Hiromu; Sano, Yuichi; Takeuchi, Masayuki; Sakauchi, Nobuyuki; Hoshi, Masayuki; Ogino, Hideki; Aose, Shinichi
no journal, ,
As a part of studies on corrosion resistance of storage tanks for flock generated in the coagulation process for radioactive contaminated water from the Fukushima Daiichi Nuclear Power Plant, several corrosion tests considering the radiation and the contact with flock were carried out with SS400 in the settling condition. Average corrosion rates of SS400 were around 0.1mm/y and severe corrosion including local corrosion was not observed.
Ambai, Hiromu; Sano, Yuichi; Takeuchi, Masayuki; Sakauchi, Nobuyuki; Hoshi, Masayuki; Ogino, Hideki; Koizumi, Kenji
no journal, ,
We studied the corrosion behavior of the tank material SS400 for flock storage in fluid flow condition by air agitation. Fluid flow increased the corrosion rate and this effect was reduced by the presence of the flock. Decreasing of flow rate and change of air to inactive gas are effective in corrosion prevention measures.
Ouchi, Masayuki; Hoshi, Takahiro; Sasaki, Shunichi; Isobe, Hiroyasu; Nagaoka, Shinichi; Kurabayashi, Kazuaki; Obu, Tomoyuki
no journal, ,
Plutonium nitrate solution is stored in tanks that have cooling system to prevent boiling accident by decay heat and scavenging system to prevent explosion of hydrogen generated by radiolysis. These systems are designed to be provided power from emergency power generators at the Tokai Reprocessing Plant (TRP) when commercial power is lost. In addition, some apparatus (mobile power generators and nitrogen gas cylinder to scavenge hydrogen, etc.) are recently deployed at TRP on the basis of power loss in Fukushima Daiichi nuclear accident. In this report, these safety measures for emergency are shown.
Hoshi, Takahiro; Nagaoka, Shinichi; Kudo, Atsunari; Ouchi, Masayuki; Isobe, Hiroyasu; Obu, Tomoyuki; Kurabayashi, Kazuaki
no journal, ,
no abstracts in English
