Results of irradiation of (U0.55Pu0.45)N and (U0.4Pu0.6)N fuels in BOR-60 up to similar to 12 at.% burn-up

• Published in: Journal of nuclear materials Vol. 440; no. 1-3; pp. 445 - 456
• Main Authors: Rogozkin, B D, Stepennova, N M, Fedorov, YuYe, Shishkov, M G, Kryukov, F N, Kuzmin, S V, Nikitin, ON, Belyaeva, A V, Zabudko, L M
• Format: Journal Article
• Language: English
• Published: 01-09-2013
• ISSN: 0022-3115
• DOI: 10.1016/j.jnucmat.2013.04.033

In the article presented are the results of post-irradiation tests of helium bonded fuel pins with mixed mononitride fuel (U0.55Pu0.45)N and (U0.4Pu0.6)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 mu m. Swelling rates of (U0.4Pu0.6)N and (U0.55Pu0.45)N were, respectively, similar to 1.1% and similar to 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.