Development of SiO2 based doped with LiF, Cr2O3, CoO4 and B2O3 glasses for gamma and fast neutron shielding

Aygun B., Şakar E., Karabulut A., Alim B., Sayyed M., Singh V. P., ...Daha Fazla

RADIOCHIMICA ACTA, cilt.109, sa.2, ss.143-151, 2021 (SCI-Expanded) identifier identifier

  • Yayın Türü: Makale / Tam Makale
  • Cilt numarası: 109 Sayı: 2
  • Basım Tarihi: 2021
  • Doi Numarası: 10.1515/ract-2020-0067
  • Dergi Adı: RADIOCHIMICA ACTA
  • Derginin Tarandığı İndeksler: Science Citation Index Expanded (SCI-EXPANDED), Scopus, Analytical Abstracts, Applied Science & Technology Source, Chemical Abstracts Core, INSPEC
  • Sayfa Sayıları: ss.143-151
  • Anahtar Kelimeler: GEANT4, glasses, Monte Carlo, neutron and gamma, shielding, X-RAY, ATTENUATION COEFFICIENTS, RADIATION, OXIDE, COMPOSITES, CONCRETE, WINXCOM, DESIGN, SYSTEM, ALLOYS
  • Atatürk Üniversitesi Adresli: Evet

Özet

In this study, the fast neutron and gamma-ray absorption capacities of the new glasses have been investigated, which are obtained by doping CoO,CdWO4,Bi2O3, Cr2O3, ZnO, LiF,B2O3 and PbO compounds to SiO2 based glasses. GEANT4 and FLUKA Monte Carlo simulation codes have been used in the planning of the samples. The glasses were produced using a well-known melt-quenching technique. The effective neutron removal cross-sections, mean free paths, half-value layer, and transmission numbers of the fabricated glasses have been calculated through both GEANT4 and FLUKA Monte Carlo simulation codes. Experimental neutron absorbed dose measurements have been carried out. It was found that GS4 glass has the best neutron protection capacity among the produced glasses. In addition to neutron shielding properties, the gamma-ray attenuation capacities, were calculated using newly developed Phy-X/PSD software. The gamma-ray shielding properties of GS1 and GS2 are found to be equivalent to Pb-based glass.