Radiation Physics and Engineering
A peer-reviewed journal published by K. N. Toosi University of Technology

Characterization of waste materials and its application towards sustainable radiation protection

Articles in Press

Document Type : Research Article

Authors

Surendra Hangsarumba 1
Bishnu Neupane 2
Raman Kumar Kamat 1
Santosh Kumar Das 1
Saddam H Dhobi 1
Buddha Ram Shah 2

1 Department of Physics, Patan Multiple Campus, Tribhuvan University, Patandhoka, Lalitpur, Nepal

2 Nepal Academy of Science and Technology, Khumaltar, Lalitpur, Nepal

https://doi.org/10.22034/rpe.2026.552271.1307
Abstract
Radiation shielding is essential for minimizing exposure to harmful ionizing radiation by employing materials that effectively absorb or block radiation. This study investigates the shielding potential of five waste-derived materials -human hair, waste glass, plastic, waste cement, and medical gloves- against β and γ radiations emitted from Thallium-204, Cesium-137, Strontium-90, and Cobalt-60 sources. Circular disc samples (2 ± 0.2 mm thick, 20 ± 0.08 mm diameter, 0.8 ± 0.11 g) were prepared in pure and composite forms (0–100 wt%). Shielding properties were quantified using a GM counter and gamma spectrometry, while structural and functional characterizations were performed using X-ray diffraction (XRD) and Fourier-transform infrared spectroscopy (FTIR). Results show that waste cement exhibited the highest shielding efficiency with η = 27.61% and AF = 1.38 at 100 wt%, effectively reducing Sr-90 penetration below ~0.90 counts/s. Medical gloves showed moderate but consistent attenuation (η ≈ 24.32%, AF ≈ 1.32), whereas hair and plastic demonstrated weaker performance (η = 10.00–25.59%, AF = 1.12–1.34). Glass exhibited low shielding capacity due to its intrinsic radioactivity (η = 1.58%, AF = 1.02). FTIR and XRD analyses confirmed that inorganic groups such as Si–O, CO₃²⁻, and SO₄²⁻ in cement and glass enhance density and rigidity, improving photon attenuation, while polymeric and organic matrices offer limited protection. Transmission studies using Co-60 validated that none of the low-density materials achieved attenuation beyond 28%. Overall, waste cement demonstrates strong potential for sustainable, low-cost radiation shielding, which can be further enhanced through composite reinforcement with dense waste materials.

Highlights

  • Waste cement showed the highest shielding (η = 27.61%, AF = 1.38), reducing Sr-90 radiation below ∼ 0.90 counts.s−1.
  • Medical gloves provided moderate and stable attenuation (η ≈ 24.32%, AF ≈ 1.32).
  • Human hair and plastic exhibited low and inconsistent shielding (η = 10.00 − 25.59%).
  • Waste glass showed poor shielding (η = 1.58%, AF = 1.02) due to intrinsic radioactivity.
  • It was found inorganic bonds (Si-O, CO2−3, SO2−4) improve photon attenuation, and organic matrices are less effective.

Keywords

Radiation shielding
Waste materials
GM counter and gamma spectrometry
XRD
FTIR
Shielding effectiveness
Attenuation factor

Subjects

Copyright
RPE is licensed under a Creative Commons Attribution-NonCommercial 4.0 International License (CC BY-NC 4.0).

Conflict of Interest
The authors declare no potential conflict of interest regarding the publication of this work‎.

Funding
‎The authors declare that no funds‎, ‎grants‎, ‎or other financial support were received during the preparation of this manuscript‎.

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Radiation Physics and Engineering

Articles in Press, Accepted Manuscript
Available Online from 30 January 2026

  • Receive Date 09 October 2025
  • Revise Date 28 January 2026
  • Accept Date 29 January 2026

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