Post-reactor studies of plutonium mononitride and oxide fuel with an inert matrix and burnup of about 19% h.a. in BOR-60

An experiment investigating the behavior of different fuel compositions with high content of plutonium for the conditions of a BOR-60 reactor was performed in 1996–2007. The results of post-reactor studies of the experimental fuel elements with 40% PuN + 60% ZrN and 40% PuO 2 + 60% MgO are presented...

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Published inAtomic energy (New York, N.Y.) Vol. 109; no. 6; pp. 369 - 374
Main Authors Rogozkin, B. D., Stepennova, N. M., Fedorov, Yu. E., Shishkov, M. G., Kryukov, F. N., Kuzmin, S. V., Nikitin, O. N., Kurina, I. S., Zabudko, L. M., Noirot, J., Bejaoui, S.
Format Journal Article
LanguageEnglish
Published Boston Springer US 01.04.2011
Springer
Springer Nature B.V
Subjects
Fission products
Hadrons
Heat conductivity
Heavy Ions
Nuclear Chemistry
Nuclear Energy
Nuclear fuels
Nuclear Physics
Physics
Physics and Astronomy
Plutonium
Radiation
Reactors
Research centers
Studies
Wire
Russia
Fuel Element
Fuel Assembly
Plutonium
Crystal Lattice Parameter
Fission Product
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Summary:An experiment investigating the behavior of different fuel compositions with high content of plutonium for the conditions of a BOR-60 reactor was performed in 1996–2007. The results of post-reactor studies of the experimental fuel elements with 40% PuN + 60% ZrN and 40% PuO 2 + 60% MgO are presented here. The microstructure, density change, crystal lattice parameters of the fuel compositions, and the fission product distribution were investigated. Burnup ~19% was attained. The swelling per 1% burnup of the fuel was 0.1% for the nitride composition and 0.7–0.9% for the oxide composition. The gas release did not exceed 1% for the nitride fuel and 9% for the oxide fuel.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-011-9370-z