Neutron radiation shielding with PUR composites loaded with B₄C or graphite

Abstract

The thermal neutron radiation shielding effectiveness of polyurethane (PUR) composites loaded with 20.9% by weight of boron carbide or by 20.4% graphite micronized fillers was evaluated. As expected, the former composite was found very effective in thermal neutron radiation shielding, and its performances were compared with those of other PUR composites loaded with about 20% of amorphous boron or 20% boron nitride. On the other hand the PUR composite loaded with graphite was found not suitable for shielding thermal neutrons. FT-IR spectroscopy and DSC were used to demonstrate the excellent neutron radiation resistance of the PUR composites of this study.

Keywords:

• Thermal neutrons
• radiation shielding
• polyurethane composites
• boron carbide
• graphite