Nitration by a simulated fuel technique for nitride fuel re-fabrication

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Nitration reaction of a spent nuclear oxide fuel through a carbothermic reduction and the change in thermal conductivity of the resultant nitride specimens were investigated by a simulated fuel technique for use in nitride fuel re-fabrication from spent oxide fuel. The simulated spent oxide fuel was formed by compacting and sintering a powder mixture of UO(2) and stable oxide fission product impurities. It was pulverized by a 3-cycle successive oxidation-reduction treatment and converted into nitride pellet specimens through the carbothermic reduction. The rate of the nitration reaction of the Simulated spent oxide fuel was decreased due to the fission product impurities when compared with pure uranium dioxide. The amount of Ba and Sr in the simulated spent oxide fuel was considerably reduced after the nitride fuel refabrication. The thermal conductivity of the nitride pellet specimen in the range 295-373 K was lower than that of the pure uranium nitride but higher than the simulated spent oxide fuel containing fission product impurities. (C) 2009 Published by Elsevier B.V.
Publisher
ELSEVIER SCIENCE BV
Issue Date
2009-07
Language
English
Article Type
Article; Proceedings Paper
Keywords

THERMAL-CONDUCTIVITY; NUCLEAR-FUEL; ENRICHMENT; EXCHANGE; BEHAVIOR; SIMFUEL; ISOTOPE; PELLETS; BURNUP

Citation

JOURNAL OF NUCLEAR MATERIALS, v.392, no.2, pp.171 - 175

ISSN
0022-3115
DOI
10.1016/j.jnucmat.2009.03.042
URI
http://hdl.handle.net/10203/255635
Appears in Collection
NE-Journal Papers(저널논문)
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