High-Temperature Behavior of Irradiated Dispersion Fuel Rods with 42KhNM-Alloy Cladding

• Published in: Atomic energy (New York, N.Y.) Vol. 130; no. 4; pp. 220 - 223
• Main Authors: Kulakov, G. V., Konovalov, Yu. V., Vatulin, A. V., Kosaurov, A. A., Shishin, V. Yu, Shel’dyakov, A. A., Romanov, A. I., Morozov, O. A., Samoilov, O. B.
• Format: Journal Article
• Language: English
• Published: New York Springer US 01.08.2021; Springer; Springer Nature B.V
• Subjects: Chromium; Chromium nickel alloys; Cladding; Ductility; Energy industry; Experiments; Fission products; Hadrons; Heavy Ions; High temperature; Irradiation; Measurement; Nickel; Nickel alloys; Nuclear Chemistry; Nuclear Energy; Nuclear fuel elements; Nuclear fuels; Nuclear Physics; Nuclear power plants; Physics; Physics and Astronomy; Pressure reduction; Radiation; Specialty metals industry; Uranium; Zirconium alloys
• ISSN: 1063-4258; 1573-8205
• DOI: 10.1007/s10512-021-00798-5

Thermal testing of shortened fuel rods with 42KhNM chromium–nickel alloy cladding, pre-irradiated in the MIR reactor to fission product content 0.9 g/cm 3 , was conducted at SSC RIAR. The mechanism of fuel rod depressurization was determined. It was shown that depressurization is associated with changes occurring in the fuel kernel at an elevated temperature, while in the 42KhNM alloy cladding practically no structural changes occur on holding for 1 h at 600°C. A relation is obtained for evaluating the possibility of and time to depressurization of a fuel rod at a specified temperature taking preliminary irradiation into account.