Journal
ATOMIC ENERGY
Volume 128, Issue 1, Pages 24-29Publisher
SPRINGER
DOI: 10.1007/s10512-020-00645-z
Keywords
-
Categories
Ask authors/readers for more resources
Work has been performed as part of the implementation of measures to reduce the hazard of irradiated graphite during the decommissioning of uranium-graphite nuclear reactors. Electrochemical decontamination is studied as a method of purifying the indicated wastes from radioactive contamination. The results of experiments on removing(60)Co,Cs-134,Cs-137,Eu-154, and(241)Am from the surface of irradiated graphite under different conditions are presented. It is shown that electrochemical decontamination of irradiated nuclear graphite in an acidic medium makes it possible to reduce the activity of(60)Co by a factor of 2-10 and Cs by a factor of 7-100 without gaseous products of reaction being formed.
Authors
I am an author on this paper
Click your name to claim this paper and add it to your profile.
Reviews
Recommended
No Data Available