Results of irradiation of (Ub>0.55b>Pub>0.45b>)N and (Ub>0.4b>Pub>0.6b>)N fuels in BOR-60 up to ¡«12 at. % burn-up

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• 作者：B.D. Rogozkin ; N.M. Stepennova ; Yu.Ye. Fedorov ; M.G. Shishkov ; F.N. Kryukov ; S.V. Kuzmin ; O.N. Nikitin ; A.V. Belyaeva ; L.M. Zabudko
• 刊名：Journal of Nuclear Materials
• 出版年：2013
• 出版时间：September, 2013
• 年：2013
• 卷：440
• 期：1-3
• 页码：445-456
• 全文大小：4511 K

文摘

In the article presented are the results of post-irradiation tests of helium bonded fuel pins with mixed mononitride fuel (Ub>0.55b>Pub>0.45b>)N and (Ub>0.4b>Pub>0.6b>)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 ¦Ìm. Swelling rates of (Ub>0.4b>Pub>0.6b>)N and (Ub>0.55b>Pub>0.45b>)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.