Developing new high-temperature shielding materials for neutron radiation protection

In this paper, neutron shields based on hydraulic lime-based brick samples were fabricated by adding various mass additive materials in proportions such as lime (CaCO3), titanium oxide (TiO2), hematite (Fe2O3), aluminum oxide (Al2O3), calcium sulfate (CaSO4), silicon dioxide (SiO2), and boron carbide (B4C). Neutron attenuation factors such as neutron transmission factor, half-value layer, effective removal cross-section Sigma R (cm-1), mean free path, and neutron flux were determined theoretically using Monte Carlo simulation GEANT4 and Fluka codes. Fast neutron absorption dose rate experiments were performed using a 241Am-Be source and a BF3 gaseous proportional detector. In addition, the absorbed dose values were theoretically determined using the Fluka code. All the obtained data were compared with the results of the examined reference samples (conventional concrete, some heavy concretes, and paraffin). All new brick materials were detected to have superior shielding capacities compared to the reference material. The proposed brick samples can be used as an alternative radiation protection material for regular shielding materials.

Dergi

RADIATION PROTECTION DOSIMETRY

Yıl

2026

Cilt

202

Sayı

5

Sayfa

468-478

ISSN

0144-8420

eISSN

1742-3406

DOI

10.1093/rpd/ncaf148

WoS UID

WOS:001642829100001