FIELD: metallurgy.
SUBSTANCE: invention relates to metallurgy of nuclear fuel, in particular to a method of producing fuel material of high purity (not less than 99 wt.%) based on zirconium-uranium alloy with high content of zirconium (60 wt.% and more) with homogeneous distribution of components in volume of material. Method includes making at least one press assembly consisting of a central rod of metallic uranium, the content of which is not more than 40 wt.%, enclosed in a zirconium bushing with end plugs, press-assembly sealing and production of bimetallic electrode by means of press-assembly hot pressing at temperature (0.52-0.55) Tmelt of uranium. Obtained bimetallic electrode is remelted by crucible-free zone melting with electron-beam heating at temperature of (0.91-0.97) Tmelt of zirconium to obtain a zirconium-uranium alloy ingot. Several ingots of fuel material can be connected to each other along end surfaces. Fuel material can be subjected to further processing, which consists in combination or application of one of the following processing methods: mechanical, thermal, electrochemical, turning, welding.
EFFECT: obtaining fuel material based on zirconium-uranium alloy with purity of not less than 99 wt % with high content of zirconium and homogeneous distribution of components in the volume of the material.
4 cl, 1 tbl, 2 ex
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URANIUM-BASED ALLOY (OPTIONS) | 2021 |
|
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RU2713619C1 |
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RU2800271C1 |
Authors
Dates
2025-04-02—Published
2024-08-27—Filed