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Oral presentation

Recent progress of research on pyrochemical process for nitride fuel cycle in JAEA

Sato, Takumi; Hayashi, Hirokazu; Shibata, Hiroki; Iwai, Takashi; Akabori, Mitsuo; Arai, Yasuo; Minato, Kazuo

no journal, , 

Recent progress of research on pyrochemical process for nitride fuel cycle in JAEA is summarized. The electrochemical behaviors in LiCl-KCl eutectic melt of burnup-simulated UN containing representative solid fission product elements (Mo, Pd, Nd) and actinide nitrides containing inert matrix materials such as (U,Zr)N, (Pu,Zr)N, UN+TiN and PuN+TiN were clarified for the first time. The behavior of Am on the electrolysis of AmN in LiCl-KCl eutectic melt and that on nitride formation of Am recovered in the liquid Cd cathode were investigated.

Oral presentation

Spectrophotometry and cyclic voltammetry of uranium ions in molten Li$$_{2}$$MoO$$_{4}$$-Na$$_{2}$$MoO$$_{4}$$ eutectic at 550 $$^{circ}$$C

Nagai, Takayuki; Uehara, Akihiro*; Fukushima, Mineo; Myochin, Munetaka; Yamana, Hajimu*

no journal, , 

In this study, absorption spectra of uranium ions on molten Li$$_{2}$$MoO$$_{4}$$-Na$$_{2}$$MoO$$_{4}$$ eutectic at 550 $$^{circ}$$C were measured by spectrophotometry, and the cyclic voltammetry was also carried out. As the results of the spectrophotometry, the observed spectra of uranium ions in the melt were similar to those of UO$$_{2}$$$$^{+}$$ in molten chlorides. After purging oxygen gas into the melt, the absorption peaks of UO$$_{2}$$$$^{+}$$ decreased and UO$$_{2}$$$$^{+}$$ was thought to be oxidized to UO$$_{2}$$$$^{2+}$$. In measurement of voltammograms in a pure melt, it was confirmed that alkali metals deposited at -0.7 V and the molybdenum oxides deposited at 1.0 V, and a small reductive reaction of this pure melt was observed at -0.3 V. When UO$$_{2}$$ was dissolved into the melt, the reduction of uranium ions was observed at -0.2 V. Therefore, it was suggested that the uranium ions in the melts will be recovered as mixed uranium-molybdenum oxides by electrolysis.

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