Open AccessReactor graphite processing in low-temperature gas-discharge plasma
Author(s) -
M. R. Shavaleev,
Н. М. Барбин,
D. I. Terentyev,
M. P. Dalkov,
S. G. Alexeev
Publication year - 2019
Publication title -
journal of physics. conference series
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.21
H-Index - 85
eISSN - 1742-6596
pISSN - 1742-6588
DOI - 10.1088/1742-6596/1370/1/012028
Subject(s) - graphite , radionuclide , inert gas , fission products , atmosphere (unit) , nitrogen , radiochemistry , uranium , materials science , carbon fibers , nuclear graphite , plasma , nuclear engineering , waste management , environmental science , chemistry , nuclear physics , metallurgy , composite material , physics , engineering , organic chemistry , thermodynamics , composite number
Graphite elements of nuclear power plants accumulate in time a small amount of uranium, radionuclide conversion elements, as well as fission products, which creates additional difficulties in the utilization of graphite masonry. We proposed a new method of processing, based on high-temperature separation in a nitrogen atmosphere. The processing consists in heating the radioactive graphite in an inert nitrogen atmosphere to a temperature of 2873 K, which creates the necessary conditions for the separation of radionuclides from carbon.