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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:1 Percentile:14.27(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

Thermodynamic approach for iron phosphate glass as a waste medium

Amamoto, Ippei; Kobayashi, Hidekazu; Yamashita, Teruo; Nagai, Takayuki; Kitamura, Naoto*; Takebe, Hiromichi*; Mitamura, Naoki*; Tsuzuki, Tatsuya*; Fukayama, Daigen*; Nagano, Yuichi*; et al.

no journal, , 

no abstracts in English

Oral presentation

Construction of Glass Database, 1; Acquisition of required thermodynamic properties for the construction of computational phase diagrams of vitrified wastes

Amamoto, Ippei; Oyama, Koichi; Nagano, Yuichi*; Jantzen, T.*; Hack, K.*; Fukayama, Daigen*

no journal, , 

As the vitrified study of the high-level radioactive waste is usually carried out under the high-temperature circumstance, it spends a lot of time and effort. The actual experiments and/or measurement, therefore, should be undertaken rationally after ascertaining the behaviors of target materials by the theoretical calculation, if possible. From such point of view, the construction of phase diagrams is considered after obtaining necessary thermodynamic properties from existing phase diagrams by CALPHAD method and/or published data. In this paper, several phase diagrams are presented such as the borosilicate glass which is currently used as the vitrified medium for the HLW, the iron-phosphate glass which will be potential vitrified medium for various wastes. Some phase diagrams are also prepared for the vitrified wastes which was loaded fission products such as molybdenum, palladium, etc..

Oral presentation

Basic research programs of vitrification technology for waste volume reduction, 58; Construction of thermodynamic database of Ru-Rh-Pd-SiO$$_{2}$$-B$$_{2}$$O$$_{3}$$-Na$$_{2}$$O-Li$$_{2}$$O system

Amamoto, Ippei; Oyama, Koichi; Fukayama, Daigen*; Nagano, Yuichi*; Hack, K.*; Jantzen, T.*

no journal, , 

The thermodynamic data of glass medium and FP, essential for estimation of the technical development of HLW as vitrified waste, is obtained by the CALPHAD method. As Ru-Rh-Pd-SiO$$_{2}$$-B$$_{2}$$O$$_{3}$$-Na$$_{2}$$O-Li$$_{2}$$O system could be constructed this time, it became possible to construct the phase diagram and/or estimation of FP loading amount under various conditions.

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