Results of U0.55Pu0.45N and U0.4Pu0.6N mixed mononitride fuel tests in a bor-60 reactor to burnup 12% h.a

The results of post-reactor studies of U 0.55 Pu 0.45 N and U 0.4 Pu 0.6 N mixed mononitride fuel elements (density 85% of the theoretical value) and a helium sublayer are presented. The fuel elements are irradiated in a BOR-60 reactor to burnup 9.4 and 12.1% h.a., respectively, with power density 4...

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Published inAtomic energy (New York, N.Y.) Vol. 110; no. 6; pp. 412 - 429
Main Authors Rogozkin, B. D., Stepennova, N. M., Fedorov, Yu. E., Shishkov, M. G., Kryukov, F. N., Kuzmin, S. V., Nikitin, O. N., Belyaeva, A. V., Zabudko, L. M.
Format Journal Article
LanguageEnglish
Published Boston Springer US 01.10.2011
Subjects
Hadrons
Heavy Ions
Nuclear Chemistry
Nuclear Energy
Nuclear Physics
Physics
Physics and Astronomy
Fuel Element
Fuel Kernel
Fuel Assembly
Plutonium
Fission Product
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Summary:The results of post-reactor studies of U 0.55 Pu 0.45 N and U 0.4 Pu 0.6 N mixed mononitride fuel elements (density 85% of the theoretical value) and a helium sublayer are presented. The fuel elements are irradiated in a BOR-60 reactor to burnup 9.4 and 12.1% h.a., respectively, with power density 430 and 540 W/cm. All fuel elements remained hermetic; the ChS-68 steel cladding (20% cold deformation) retained excess plasticity. The maximum zone of interaction between the cladding and the fuel and fission products did not exceed 15 μm. The swelling rate of U 0.4 Pu 0.6 N and U 0.55 Pu 0.45 N fuel was 1.1 and 0.68%/% burnup, respectively. The gas release did not exceed 19.3 and 19%. The steel damage dose was 43 dpa. The character of the porosity distribution in the fuel affects the swelling and gas release.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-011-9442-0