MONTE-CARLO (MC) ANALYSIS OF BORATED MATERIALS FOR NEUTRON SHIELDING APPLICATIONS

Author:

ALBARODİ Abdulrahman,USLU KİÇECİ Pelin,UZUN DURAN Selcen1,DEMİRKÖZ Bilge2

Affiliation:

1. KARADENİZ TEKNİK ÜNİVERSİTESİ

2. Orta Doğu Teknik Üniversitesi

Abstract

Neutron shielding is of utmost importance in radiation environments such as nuclear reactors and particle accelerators and in fields such as health physics. In this work, the percentages of neutrons stopped by shields comprising of boron minerals (HDPE/B2O3, Epoxy/Priceite, Epoxy/Colemanite, Epoxy/Kernite) in their composition against neutron radiation of different energies is investigated using two separate MC simulations. Different layer combinations of epoxy based borated shielding materials with HDPE sheets were then simulated to find the optimum shielding configuration. In addition, radioactivation studies were carried out for these designs. The most suitable design was found to be the layered setup of the HDPE sheet and the epoxy/colemanite composite sheet for mixed neutron energies (

Publisher

Omer Halisdemir Universitesi

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