Study of The Reactor Graphite Samples (GR-280) Surface Morphological Properties

In this paper we have studied surface elemental composition and morphological properties of the unirradiated reactor graphite by means of Scanning Electron Microscopy (SEM) with X-ray microanalysis and Brunauer-Emmett-Teller (BET) method. The data obtained are of interest for understanding properties of the near-surface reactor graphite layers during its operation in the RBMK reactor and possible graphite deactivation in dismantling period. For example, gaseous nitrogen diffusion into the near-surface reactor graphite layer with the following neutron irradiation provides significant accumulation of
¹⁴
C isotope in this layer. Also some graphite surface depot contaminated by some metal atoms may provide extra radiation level. In this view, irradiated reactor graphite blocks containing increased surface concentration of
¹⁴
C and other isotopes can be specifically treated with “dry” ion-plasma deactivation technology followed by the concentrated extraction of
¹⁴
C and some gamma-radiating isotopes for their useful application. and for creation of a new generation of materials. Thus, the knowledge of the reactor graphite surface properties ensures basics for the ion-plasma decontamination technology and for the controlled fabrication of new nanomaterials like a beta-active “nano-micro-sandwich” (enriched with radioisotope
¹⁴
C) for betavoltaic batteries, brachytherapy in the nuclear medicine and isotopes for radiative sterilization.