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The main results of development work and post-reactor studies of different structural materials for fuel-element cladding and hexahedral fuel-assembly jackets for sodium-cooled fast reactors are examined. Austenitic and ferritic-martensitic steels, including steel obtained by powder metallurgy, are examined as promising materials for fuel-element cladding for staged increase of fuel burnup.
Since its startup in December in 1969, the BOR-60 reactor has been used effectively for irradiation of structural and fuel materials in a wide range of dose–temperature parameters. Analysis of the actual computational-experimental parameters (irradiation temperature, damage rates) shows that the irradiation conditions are highly reproducible and can be maintained accurately. The investigations made...
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