Investigation of neutron shielding properties depending on number of boron atoms for colemanite, ulexite and tincal ores by experiments and FLUKA Monte Carlo simulations

Korkut T., KARABULUT A., BUDAK G., Aygun B., GENÇEL O., HANÇERLİOĞULLARI A.

APPLIED RADIATION AND ISOTOPES, cilt.70, sa.1, ss.341-345, 2012 (SCI-Expanded) identifier identifier identifier

  • Yayın Türü: Makale / Tam Makale
  • Cilt numarası: 70 Sayı: 1
  • Basım Tarihi: 2012
  • Doi Numarası: 10.1016/j.apradiso.2011.09.006
  • Dergi Adı: APPLIED RADIATION AND ISOTOPES
  • Derginin Tarandığı İndeksler: Science Citation Index Expanded (SCI-EXPANDED), Scopus
  • Sayfa Sayıları: ss.341-345
  • Anahtar Kelimeler: Boron ores, Neutron shielding, Total macroscopic cross section, FLUKA Monte Carlo code, HVL, DOSE TRANSMISSION, CROSS-SECTIONS, CONCRETE, ATTENUATION
  • Atatürk Üniversitesi Adresli: Evet

Özet

Am-241-Be source and three samples including different amounts of boron atoms per unit volume called colemanite, ulexite and tincal were used in total macroscopic cross section experiments. Also FLUKA Monte Carlo code was used to simulate total macroscopic cross sections, absorbed doses and deposited energies by low energy neutron interactions. Besides half value layers of samples were calculated and compared to paraffin. As a result, ascending concentration of boron atoms can enhance neutron shielding property of samples. (C) 2011 Elsevier Ltd. All rights reserved.