METHOD FOR OBTAINING URANIUM GRAPHITE FUEL ROD Russian patent published in 2022 - IPC G21C21/02 

Abstract RU 2787077 C1

FIELD: nuclear fuel technology.

SUBSTANCE: invention can be used to obtain uranium graphite fuel elements for high-temperature gas cooled nuclear reactors. A method for producing an uranium graphite fuel element includes preparing a charge by mixing graphite powder, phenol-formaldehyde resin and micro-fuel elements which are preliminary coated with a layer of graphite powder with a thickness of at least 0,25 of the MF diameter before batch preparation. Blanks are formed by pressing and heat treatment in a mold under a pressure of 10-15 MPa, raising the temperature to 250-300 °C, after which the pressure is removed before removing the workpieces from the molds. Then the carbonization of the resin and high-temperature heat treatment are carried out.

EFFECT: reduction of rejects due to the prevention of cracking and distortion in the manufacture of a cylindrical uranium-graphite fuel element with an increased volume fraction of micro-fuel elements (more than 20% by vol.).

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RU 2 787 077 C1

Authors

Lysenko Evgenij Konstantinovich

Fedin Oleg Igorevich

Marushkin Dmitrij Valerevich

Cherkasov Aleksandr Sergeevich

Chumak Lesya Grigorevna

Drobyazko Petr Vladimirovich

Dates

2022-12-28Published

2022-07-27Filed