Short-Time Mechanical Properties of EP823-SH Ferrite-Martensite Steel After High-Dose Neutron Irradiation

Irradiation of experimental fuel assemblies with uranium-plutonium nitride fuel and shells made of ferritic- martensitic steel EP823-Sh is conducted in order to ensure normal operation of BREST-OD-300 fuel rods in the BOR-60 and BN-600 reactors. This article presents the results of an investigation...

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Bibliographic Details
Published in:Atomic energy (New York, N.Y.) N.Y.), 2021-10, Vol.130 (6), p.323-327
Main Authors: Grachev, A. F., Zabud’ko, L. M., Leont’eva-Smirnova, M. V., Naumenko, I. A., Kryukov, F. N., Chertopyatov, E. V., Marinenko, E. E., Porollo, S. I.
Format: Article
Language:English
Subjects:
Corrosion and anti-corrosives
Hadrons
Heavy Ions
Iron compounds
Mechanical properties
Nitrides
Nuclear Chemistry
Nuclear Energy
Nuclear Physics
Nuclear power plants
Nuclear reactors
Physics
Physics and Astronomy
Radiation
Steel
Uranium
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Summary:Irradiation of experimental fuel assemblies with uranium-plutonium nitride fuel and shells made of ferritic- martensitic steel EP823-Sh is conducted in order to ensure normal operation of BREST-OD-300 fuel rods in the BOR-60 and BN-600 reactors. This article presents the results of an investigation of the short-time mechanical properties of fuel rod cladding made of EP823-Sh steel after irradiation in BOR-60 and BN-600 reactors at temperatures 315–610°C up to maximum damaging dose 94 dpa, obtained for circular and longitudinal segmented samples. Empirical temperature dependences are proposed for the ultimate strength and total relative elongation of the irradiated EP823-Sh steel.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-022-00818-y