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

• Published in: Atomic 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
• Language: English
• 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
• ISSN: 1063-4258; 1573-8205
• DOI: 10.1007/s10512-011-9442-0

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.