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Updated: Jan 8, 2026

Laser-heating and Radiance Spectrometry for the Study of Nuclear Materials in Conditions Simulating a Nuclear Power Plant Accident

Laser-heating and Radiance Spectrometry for the Study of Nuclear Materials in Conditions Simulating a Nuclear Power Plant Accident

Published on: December 14, 2017

中性子放射線防護のための新しい高温遮蔽材料の開発

Bünyamin Aygün¹, Turgay Korkut², Eren Urtekin³

¹Department of Electronics and Automation, Vocational School, Agri Ibrahim Cecen University, 04000 Agri, Türkiye.

Radiation protection dosimetry

|December 20, 2025

Abstract:

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 ΣR (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.

キーワード:

中性子遮蔽水硬性石灰放射線防護材料科学原子力工学

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