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Journal Articles

Research on vitrification technology to immobilize radioactive sludge generated from Fukushima Daiichi Power Plant; Enhanced glass medium

Amamoto, Ippei; Kobayashi, Hidekazu; Kitamura, Naoto*; Takebe, Hiromichi*; Mitamura, Naoki*; Tsuzuki, Tatsuya*; Fukayama, Daigen*; Nagano, Yuichi*; Jantzen, T.*; Hack, K.*

Journal of Nuclear Science and Technology, 53(10), p.1467 - 1475, 2016/10

 Times Cited Count:4 Percentile:28.09(Nuclear Science & Technology)

The iron phosphate glass (IPG) medium is known to be a high-efficiency glass medium, therefore we try to evaluate its applicability to immobilize sludge bearing radioactive nuclides arising from treatment of contaminated water at the stricken Fukushima Daiichi Nuclear Power Plant. For this study, many physical and chemical properties of target materials are necessary to evaluate the behaviours of IPG medium and its waste forms. Inevitably, it will entail the need for many and varied types of experiments to be carried out under high temperature. It is therefore rational to apply appropriate theoretical analysis first so as to reduce the number of experimental run. For this reason, some necessary thermodynamic values for theoretical analysis were estimated by CALPHAD approach followed by making up the calculated phase diagrams. By comparison with experimental results, they were found to be reliable for evaluating the behaviours of IPG medium and its waste forms.

Oral presentation

Composition optimization of iron phosphate glasses for radioactive sludge

Takebe, Hiromichi*; Kitamura, Naoto*; Amamoto, Ippei; Kobayashi, Hidekazu; Mitamura, Naoki*; Tsuzuki, Tatsuya*

no journal, , 

The great amount of water used for cooling the stricken power reactors at Fukushima Dai-ichi following the earthquake and tsunami on March 11, 2011 has resulted in the accumulation of the remaining water. The water is subsequently contaminated by fission products and some other radioactive substances. The initial treatment to remove the radioactive substances from the cooling water again produced a secondary radioactive waste, the sludge. Iron phosphate glass powder/frit and main component of raw materials for simulated sludge, e.g., barium sulfate and potassium nickel ferrocyanide with various concentrations, were mixed for melting batch. The temperature required for the formation of homogeneous melt was determined by the direct observation of sample decomposition and melting processes on the thermocouple filament through a microscope. The mixtures for bulk glasses were melted in air using platinum crucibles. The quenched glass samples consisted mainly of oxide constituents due to the decomposition of the sludge components during heating and melting processes. Characteristic temperatures of glass transition, Tg, and onset of crystallization, Tx, was determined by differential thermal analysis. Thermal stability against crystallization for the glass samples was evaluated by the temperature difference between Tx and Tg. Water durability was determined by the weight change per a specific surface area after immersion test in hot water at 120$$^{circ}$$C for 72 hours based on MCC-2 static leaching method. Phosphate network species and chemical bonding were characterized by Raman spectroscopy. Glass composition melted with the stimulated sludge components is optimized in terms of both thermal stability and water durability with the characterization of O/P molar ratio.

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