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 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 gas from uranium nitrides dissolving in the LiCl-KCl eutectic melt reacted with CdCl above 550 C, which is higher than that for lanthanide nitrides.

Language	:	English
Journal	:	Journal of Nuclear Science and Technology
Volume	:	39
Number	:	Suppl.3
Pages	:	p.624 - 627
Publication Year/Month	:	2002/11
Meeting title	:	Actinides 2001 International Conference (ACTINIDES 2001)
Held date	:	2001/11
Location (city)	:	Hayama
Location (country)	:	Japan
Patent information	:
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Paper URL	:	http://www.tandfonline.com/doi/abs/10.1080/00223131.2002.10875545
DOI for research data	:
Keywords	:	Nitride; Fuel; Reprocessing; Molten Salts; UN; U $_{2}$ N $_{3}$
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Article of JAEA R&D Review	:
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Registration No. : B20010823
JAEA Abstracts No. : 310243
Paper Submission No. : 19873

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