Results of Studies of BN-600 Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel and ChS68-ID c.d. Steel Cladding
| Autor: | Yu. A. Ivanov, F. N. Kryukov, L. M. Zabud’ko, S. I. Porollo, O. N. Nikitin, A. F. Grachev, E. E. Marinenko, E. A. Zvir, M. V. Skupov |
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| Rok vydání: | 2019 |
| Předmět: |
Cladding (metalworking)
Materials science 020209 energy Metallurgy chemistry.chemical_element 02 engineering and technology Nitride Uranium Rod Corrosion Plutonium Nuclear Energy and Engineering chemistry 0202 electrical engineering electronic engineering information engineering Power density Burnup |
| Zdroj: | Atomic Energy. 126:182-190 |
| ISSN: | 1573-8205 1063-4258 |
| DOI: | 10.1007/s10512-019-00534-0 |
| Popis: | Reactor tests in BN-600 and post-reactor studies of experimental FA of fuel rods with mixed nitride fuel and different cladding are being conducted in Project Breakthrough. In the present article, the irradiation parameters of fuel rods with mixed nitride fuel and cladding made from ChS68-ID c.d. austenitic steel are presented: maximum linear power density 38.3 kW/m, maximum fuel burnup 7.5% h.a., and maximum damage dose 73.6 dpa. No depressurization of the fuel elements was recorded. The results of post-reactor examination (PIE) of the irradiated fuel rods are presented – swelling, gas release from fuel, and mechanical and corrosion characteristics of the cladding. |
| Databáze: | OpenAIRE |
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