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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.
Sakaguchi, Shinobu; Tachibana, Ikuya; Koshino, Katsuhiko; Shirozu, Hidetomo; Shirai, Nobutoshi; Imamoto, Nobuo; Tomita, Tsuneo; Tobita, Hiroo; Yamanaka, Atsushi; Kobayashi, Daisuke; et al.
JAEA-Technology 2011-006, 24 Pages, 2011/03
JAEA-Technology-2011-006.pdf:3.07MB
In the Niigataken Chuetsu-oki Earthquake on 2007, observed earthquake motion exceeded design base at the Kashiwazaki Kariwa nuclear plant. However, there was no earthquake damage in safety important equipments to stop reactor, to cool reactor, and to contain radioactive materials. One of this reason is said that many safety margin are included in the design and the permissible value. To know more accurate safety margin, shearing force examinations for the base bolts were conducted. In examinations, delegate test-bolts were made; the test bolts were selected from heavier equipment in Tokai Reprocessing Plant. In this report, the shearing strength obtained from the examinations shows more accurate safety margin.
Ouchi, Yasuhiro; Ito, Masatoshi; Oba, Toshinobu; Kawamata, Satoshi; Ishizaki, Katsuhiko
JAEA-Technology 2009-038, 38 Pages, 2009/07
JAEA-Technology-2009-038.pdf:2.87MB
The primary cooling system of JRR-3 is one of important facility which removes heat from reactor core. Therefore, it is necessary for safe and stable reactor operation to keep performance of four pumps which are main equipments of primary cooling system. These four pumps have been checked and maintained appropriately since the operation of JRR-3 started. Maintenance items and its records of primary cooling pumps are reported in this paper. Furthermore, aging problems of primary cooling pumps is investigated to contribute to management for maintenance of primary cooling pumps.
Nio, Daisuke; Ota, Kazunori; Ishizaki, Katsuhiko
Nihon Hozen Gakkai Dai-5-Kai Gakujutsu Koenkai Yoshishu, p.393 - 395, 2008/07
The research reactor JRR-3 was constructed for the purpose of development of nuclear technology and a large scale modification was done. It is necessary to investigate a maintenance methods considering high aging, because more than 15 years has passed from a large modification. In such situation, we should continue condition monitoring method which does not spoil safety and reliability and apply other instruments. So far, monitoring of vibration and lubricating oil has been done, and we might think it appropriate. From now on, we continue investigating that condition monitoring could be applied for other instruments.
Ishizaki, Katsuhiko; Ota, Kazunori; Takeuchi, Masaki; Imahashi, Masaki; Fukushima, Manabu
no journal, ,
no abstracts in English
