Investigation of radiation attenuation properties of Al-Cu matrix composites reinforced by different amount of B4 C particles


GOKMEN U., ÖZKAN Z., Eslam JamalGolzari L., bilge ocak s.

BOR DERGİSİ, cilt.5, sa.3, ss.124-130, 2020 (Hakemli Dergi) identifier

  • Yayın Türü: Makale / Tam Makale
  • Cilt numarası: 5 Sayı: 3
  • Basım Tarihi: 2020
  • Doi Numarası: 10.30728/boron.730354
  • Dergi Adı: BOR DERGİSİ
  • Derginin Tarandığı İndeksler: TR DİZİN (ULAKBİM)
  • Sayfa Sayıları: ss.124-130
  • Gazi Üniversitesi Adresli: Evet

Özet

In recent years, B4C particle reinforced Al matrix composite materials have beenexcessively used for gamma and neutron shielding regarding their neutron absorptionand lightweight. In this paper, linear and mass attenuation coefficients using 80 keV,356 keV, 137Cs (662 keV), 60Co (1173 keV,1332 keV) and 2000 keV(high energy)gamma energies for B4C (5-15 wt%) particle-reinforced Alumix 13 and Alumix231 (which contains special alloy elements such as Cu and Mg) aluminum matrixcomposites were theoretically calculated with XCOM platform. Pair production,coherent scattering, photoelectric absorption and incoherent scattering processesbesides the total attenuation coefficients for B4C (5-15 wt%) particle-reinforcedAlumix 13 and Alumix 231 matrix composite materials were evaluated separately.On the other hand, half-value thickness (HVL) values and one-tenth thicknessvalues (TVL) were also calculated to evaluate the radiation shielding effectivenessof this material excluding coherent scattering values that are frequently used ingamma ray transport theory as well as the total attenuation coefficients. Gammaattenuation curves for Al composite materials against 80 keV, 356 keV, 137Cs (662keV), 60Co (1173 keV, 1332 keV) and 2000 keV (high energy) gamma energies weretheoretically calculated and plotted for B4C (5-15 wt%) particle-reinforced Alumix 13and Alumix 231 matrix composite materials. According to the obtained results forthis material, radiation attenuation properties and the ability of shielding of materialswere investigated. Therefore, this study is original from a variety of aspects, and itsresults may be used not only in nuclear technology but also in other technologiessuch as nano and space technology