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Report No.

Dissolution of uranium nitrides in LiCl-KCl eutectic melt

Hayashi, Hirokazu ; Kobayashi, Fumiaki; Ogawa, Toru; Minato, Kazuo 

The behavior of the dissolution of uranium nitrides, which is a component of the MA-U mixed nitride fuel, has been investigated. A mixture of uranium nitride, LiCl-KCl and CdCl$$_2$$ was contained in a double walled quartz reaction vessel. During the heating, the carrier gas helium was introduced to a gas chromatography apparatus equipped with an automatic gas sampler. A fraction of the gas was sampled and analyzed by a mass analyzer. Most of nitrogen is recovered as N$$_2$$ gas from uranium nitrides dissolving in the LiCl-KCl eutectic melt reacted with CdCl$$_2$$ above 550 $$^o$$C, which is higher than that for lanthanide nitrides.



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