Thermal parameters investigation of neutron-irradiated nanocrystalline silicon carbide (3C-SiC) using DTA, TGA and DTG methods

Huseynov E. M., Naghiyev T., Aliyeva U. S.

PHYSICA B-CONDENSED MATTER, vol.577, 2020 (SCI-Expanded) identifier identifier

  • Publication Type: Article / Article
  • Volume: 577
  • Publication Date: 2020
  • Doi Number: 10.1016/j.physb.2019.411788
  • Journal Name: PHYSICA B-CONDENSED MATTER
  • Journal Indexes: Science Citation Index Expanded (SCI-EXPANDED), Scopus, Academic Search Premier, PASCAL, Aerospace Database, Communication Abstracts, Compendex, INSPEC, Metadex, Civil Engineering Abstracts
  • Azerbaijan State University of Economics (UNEC) Affiliated: Yes

Abstract

Nanocrystalline silicon carbide (3C-SiC) particles were irradiated by neutron flux up to 5 h at the TRIGA Mark II type research reactor. DSC (Differential Scanning Calorimetry), DTA (Differential Thermic Analysis), TGA (Thermogravimetric Analysis) and DTG (Differential Thermogravimetric Analysis) analyzes (in cooling and heating processes) of nanocrystalline silicon carbide (3C-SiC) particles were carried out before and after neutron irradiation. It was revealed that the neutron irradiation causes a change in the numerical value of heat flux. Moreover, it has been shown that the oxidation process is relatively slow due to the influence of the neutrons. It was determine that the numerical value of specific heat capacity is characteristic (500. 750 J kg(-1)K(-1)) for 3C-SiC nanocrystals.