Results of irradiation of (U(0.55)Pu(0.45))N and (U(0.4)Pu(0.6))N fuels in BOR-60 up to ~12 at.% burn-up

In the article presented are the results of post-irradiation tests of helium bonded fuel pins with mixed mononitride fuel (U(0.55)Pu(0.45))N and U(0.4)Pu(0.6))N having 85% density irradiated in BOR-60 reactor. Achieved maximum burn-up was, respectively, equal to 9.4 and 12.1 at.% with max linear hea...

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Bibliographic Details
Published in:Journal of nuclear materials 2013-01, Vol.440 (1-3), p.445-456
Main Authors: Rogozkin, B D, Stepennova, N M, Fedorov, Yu Ye, Shishkov, M G, Kryukov, F N, Kuzmin, S V, Nikitin, O N, Belyaeva, A V, Zabudko, L M
Format: Article
Language:English
Subjects:
Claddings
Density
Ductility
Fuel consumption
Fuels
Irradiation
Nuclear reactor components
Swelling
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Summary:In the article presented are the results of post-irradiation tests of helium bonded fuel pins with mixed mononitride fuel (U(0.55)Pu(0.45))N and U(0.4)Pu(0.6))N having 85% density irradiated in BOR-60 reactor. Achieved maximum burn-up was, respectively, equal to 9.4 and 12.1 at.% with max linear heat rates 41.9 and 54.5 kW/m. Maximum irradiation dose was 43 dpa. No damage of claddings made of ChS-68 steel (20% cold worked) was observed, and ductility margin existed. Maximum depth of cladding corrosion was within 15 urn. Swelling rates of U(0.4)Pu(0.6))N and (U(0.55)Pu(0.45))N were, respectively, ~1.1% and ~0.68% per 1 at.%. Gas release rate did not exceed 19.3% and 19%. Pattern of porosity distribution in the fuel influenced fuel swelling and gas release rates.
ISSN:0022-3115