Voloxidation of Mixed Nitride Uranium–Plutonium Spent Nuclear Fuel-Reference-Cited by-同舟云学术

Voloxidation of Mixed Nitride Uranium–Plutonium Spent Nuclear Fuel

Published:2023-04 Issue:2 Volume:65 Page:177-184
ISSN:1066-3622
Container-title:Radiochemistry
language:en
Short-container-title:Radiochemistry

Author:

Momotov V. N.,Makarov A. O.,Volkov A. Yu.,Lakeev P. V.,Tikhonova D. E.,Dvoeglazov K. N.

Abstract

AbstractThe efficiency of voloxidation of mixed nitride uranium–plutonium spent nuclear fuel (MNUP SNF) for the separation of the fuel composition from the fuel rod cladding and removal of3H and14C was estimated. It was shown that the completeness of SNF separation from fuel rod cladding under optimal conditions is at the level of 98–99%. The residual content of tritium in the voloxidized fuel does not exceed 0.2% of its content in the original SNF sample; radiocarbon is removed by 98%.

Publisher

Pleiades Publishing Ltd

Subject

Physical and Theoretical Chemistry

Link

https://link.springer.com/content/pdf/10.1134/S1066362223020042.pdf

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