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Gosudarstvennaya Korporatsiya po Atomnoj Ehnergii «Rosatom», Moscow (Russian Federation); Aktsionernoe Obshchestvo «Gosudarstvennyj Nauchnyj Tsentr — Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov», Dimitrovgrad (Russian Federation); 312 p; ISBN 978-5-94831-178-4; 
; 2019; p. 108-109, 110-111; 11. Conference on reactor materials science; XI konferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 27-31 May 2019; 2 figs.
; 2019; p. 108-109, 110-111; 11. Conference on reactor materials science; XI konferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 27-31 May 2019; 2 figs.
No abstract available
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Gosudarstvennaya Korporatsiya po Atomnoj Ehnergii «Rosatom», Moscow (Russian Federation); Aktsionernoe Obshchestvo «Gosudarstvennyj Nauchnyj Tsentr — Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov», Dimitrovgrad (Russian Federation); 146 p; ISBN 978-5-94831-196-8; ; 2021; p. 58-59; 10. All-Russian Youth conference ''Scientific research and technological developments to ensure the development of new generation nuclear technologies''; X Vserossijskaya molodezhnaya konferentsiya «Nauchnye issledovaniya i tekhnologicheskie razrabotki v obespechenie razvitiya yadernykh tekhnologij novogo pokoleniya»; Dimitrovgrad (Russian Federation); 17-18 Mar 2021; 2 figs.
; 2021; p. 58-59; 10. All-Russian Youth conference ''Scientific research and technological developments to ensure the development of new generation nuclear technologies''; X Vserossijskaya molodezhnaya konferentsiya «Nauchnye issledovaniya i tekhnologicheskie razrabotki v obespechenie razvitiya yadernykh tekhnologij novogo pokoleniya»; Dimitrovgrad (Russian Federation); 17-18 Mar 2021; 2 figs.
No abstract available
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Toplivnaya Kompaniya OAO TVEhL, Moscow (Russian Federation); Mezhregional'naya Obshchestvennaya Organizatsiya Nauchno-Tekhnicheskoe Obshchestvo Materialovedov (MOM), Moscow (Russian Federation); Ministerstvo Obrazovaniya i Nauki Rossijskoj Federatsii, Natsional'nyj Issledovatel'skij Yadernyj Univ. MIFI, NOTs Radiatsionnoe Materialovedenie i Radiatsionnaya Bezopasnost', Moscow (Russian Federation); 152 p; ISBN 978-5-7262-1759-8; ; 2012; p. 102; Materials for advanced reactor facilities: development and application; Materialy perspektivnykh reaktornykh ustanovok: razrabotka i primenenie; Zvenigorod (Russian Federation); 29 Oct - 2 Nov 2012
; 2012; p. 102; Materials for advanced reactor facilities: development and application; Materialy perspektivnykh reaktornykh ustanovok: razrabotka i primenenie; Zvenigorod (Russian Federation); 29 Oct - 2 Nov 2012
[en] Highlights: • Materials, irradiation parameters and research methods. • Fuel pins with nitride fuel irradiated in the BN-600 reactor. • Fuel pins with nitride fuel irradiated in BOR-60. Today the investigations have been completed on helium-bonded fuel pins with mixed uranium-plutonium nitride of BN-600/BN-800, BN-1200 and BREST reactors types after irradiation as a part of ten EFAs of BN-600 reactor up to maximum burn-up of 7.5; 6.0 and 4.5at%, respectively. Also the PIE of mixed nitride pins of BREST type with helium and lead sub-layers after intermediate tests to maximum burn-up of 4,8 and 3,9at% as part of dismountable EFAs of BOR-60 reactor are over. As a result of postirradiation examinations, the main intra-fuel pin processes that affect on materials properties change and fuel pins state, their relationship with the initial nitride state were identified. The regularities and quantitative characteristics of nitride swelling, the behavior of fission products, cladding corrosion and mechanical properties change are revealed. The average for the irradiation time rate of fuel swelling in cross sections near the core midplane in gas-bonded pins of different EFAs irradiated in BN-600 reactor is equal to (1.6 - 2.0) %/at%. According to the results of irradiation in BOR-60 reactor, the fuel swelling rate in lead-bonded pins is lower than in helium-bonded pins: 1.4 ± 0.2 and 1.7 ± 0.2 %/at%, respectively. The presence of carbon and oxygen impurities in the fuel can lead to local areas of claddings carburization and oxidation, randomly distributed along the height and perimeter of its inner surface. The key characteristics of the fuel that determine the cladding carburization and oxidation, and ways to prevent them, are determined. Cladding corrosion in lead-bonded pin is caused by selective dissolution of cladding steel components. The maximum depth of the corrosion zone is located in the upper part of the fuel column and is equal to 40 microns. The results of cladding mechanical tests obtained using longitudinal segment samples and tubular samples loaded by internal gas pressure showed the significant margin of strength and ductility of cladding materials along the entire height of fuel pins both at nominal operating temperatures and at room temperature. High values of strength characteristics indicate a weak influence of corrosion on the strength of studied claddings materials. The mechanical cladding properties of a lead – bonded pins have the same pattern of change along the pin height depending on irradiation and testing temperatures, as of fuel pins with helium sublayer, keeping enough ductility in the area of low-temperature irradiation embrittlement. So, for example, at irradiation and test temperatures of 350-380 °C, the values of the strength limit from 1070 to 1200 MPa were obtained with the values of the total elongation of not less than 2 %. Thus, the results of post-irradiation examinations confirmed the performance of mixed nitride pins at the achieved test parameters and the possibility of their irradiation prolongation to higher fuel burn-up.
Journal
[en] 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 μm. Swelling rates of (U0.4Pu0.6)N and (U0.55Pu0.45)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
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