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- 저자 : Gediminas Niaura (검색결과 2 건)
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Thermal reduction of graphite oxide in the presence of nitrogen-containing dyes
Barkauskas Jurgis,Gaidukevič Justina,Niaura Gediminas 한국탄소학회 2021 Carbon Letters Vol.31 No.6
Thermal reduction of graphite oxide (GO) is considered as a prospective method for the preparation of high-performance graphene-based materials. However, this method has certain limitations, and the major is that this exothermic process is diffcult to control. In this research, we focused on the kinetic studies of the reduction of graphite oxide using non-isothermal diferential calorimetry (DSC) method. Six GO nanocomposites with dyes were tested to study the shift in kinetic parameters. The apparent reaction order is determined to be ca 0.7 for the thermal decomposition of pure GO, while in the presence of dye molecules it increases sometimes reaching a value of 2.0 for higher dye concentrations. Decisively, the thermal decomposition of pure GO can be presented as an intermediate between a zero- and frst-order reaction, while the introduction of dye molecules turns a certain part of the energy consumption via the bimolecular pathway. Our research revealed that the process of GO thermal decomposition can be operated and properties of the fnal product (reduced graphene oxide (rGO) and its derivatives) can be adjusted more precisely using additive molecules, which interact with GO sheets.
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Structural and radiological characterization of irradiated RBMK-1500 reactor graphite
Elena Lagzdina,Danielius Lingis,Arturas Plukis,Rita Plukiene,Darius Germanas,Andrius Garbaras,Jevgenij Garankin,Arunas Gudelis,Ilja Ignatjev,Gediminas Niaura,Sergej Krutovcov,Vidmantas Remeikis 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.1
This study aims to characterize the irradiated RBMK-1500 nuclear graphite in terms of both structuraland radiological properties. The experimental results of morphological and structural analysis of theirradiated graphite samples by using SEM, Raman spectroscopy as well as the theoretical evaluation ofprimary displacement damage are presented. Moreover, the experimental and theoretical evaluation ofthe neutron flux is provided and the presence of several g emitters in the analyzed graphite samples isassessed. Furthermore, the improved version of rapid analysis method for 14C activity determination isapplied and the experimentally obtained results are compared with calculated ones. Results indicate thatstructural changes are uniform enough in all the analyzed samples. However, the distribution of radionuclidesis non-homogeneous in the irradiated RBMK-1500 reactor graphite matrix. The comprehensiveunderstanding of both structural and radiological characteristics of nuclear graphite is veryimportant when dealing with decision about irradiated graphite waste management strategy or treatmentoptions prior to its final disposal.
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