Neutron transmission analysis in borated polyethylene, boron carbide, and polyethylene: Insights from MCNP6 simulations

Almisned G., Susoy G., Tekin H.

Radiation Physics and Chemistry, cilt.218, 2024 (SCI-Expanded) identifier

  • Yayın Türü: Makale / Tam Makale
  • Cilt numarası: 218
  • Basım Tarihi: 2024
  • Doi Numarası: 10.1016/j.radphyschem.2024.111585
  • Dergi Adı: Radiation Physics and Chemistry
  • Derginin Tarandığı İndeksler: Science Citation Index Expanded (SCI-EXPANDED), Scopus, Academic Search Premier, Aerospace Database, Chemical Abstracts Core, Chimica, Communication Abstracts, Compendex, INSPEC, Metadex, Pollution Abstracts, Civil Engineering Abstracts
  • Anahtar Kelimeler: Borated polyethylene, MCNP6, Neutron shielding, Neutron transmission
  • İstanbul Üniversitesi Adresli: Evet

Özet

This study delves into the neutron transmission properties of three pivotal materials: borated polyethylene, boron carbide (B4C), and polyethylene, employing the advanced MCNP6 (version 6.2) Monte Carlo code. The primary objective was to discern the impact of boron content and material density on neutron transmission efficacy. Results highlighted the formidable neutron shielding prowess of B4C, which exhibited the lowest neutron transmission factor among the studied materials. Borated polyethylene samples revealed an inverse correlation between boron concentration and neutron transmission, emphasizing boron's paramountcy in neutron attenuation. In contrast, polyethylene showcased notable neutron moderating capabilities, necessitating synergistic integration with materials possessing higher neutron absorption cross-sections for superior neutron shielding. Material density and the presence of other elemental constituents further influenced neutron transmission. The research provides a comprehensive understanding of neutron-material interactions, setting the groundwork for enhanced safety measures in nuclear applications.