Analysis of Neutron Radiation Absorption Capacity of Coir Fiber Composite Board as A Neutron Radiation Shield

Evi Christiani  Sitepu; Dimas Frananta Simatupang

doi:10.21771/jrtppi.2025.v16.no1.p1-8

Authors

Evi Christiani Sitepu Politeknik Teknologi Kimia Industri Medan
Dimas Frananta Simatupang Politeknik Teknologi Kimia Industri

DOI:

https://doi.org/10.21771/jrtppi.2025.v16.no1.p1-8

Keywords:

Linear Attenuation Coefficient, absorption capacity, Neutron Radiation

Abstract

Research has been conducted on the radiation shielding capability of coir fiber composite boards to determine the extent of neutron radiation absorption as it passes through the created radiation shield. This study aims to ascertain whether coir fiber can be used as a filler in the production of radiation shields. Initial analysis was conducted using SEM-EDX, FTIR, and XRD testing. The results indicated that the primary component of coir fiber is carbon at 70.68%, which is structured in chemical bonds of cellulose, hemicellulose, and lignin. Additionally, coir fiber retains a crystalline region observed at the peak of 2θ=22.4°, with a crystallinity degree of 35.46%, suggesting its potential for neutron radiation absorption. After fabricating the composite board, it was tested using the Neutron Activation Analysis method to evaluate its neutron radiation absorption capability. The analysis results showed that the absorption capacity of the composite board at a fiber mass fraction of 2.0 g ranged from 59.4 to 97.8%; at 3.0 g from 64.3 to 98.3%; and at 4.0 g from 73.5 to 99.3%. The linear attenuation coefficients (µ) for each coir fiber fraction were found to be 3.84; 4.13; and 4.80/cm, with half-value layers of 0.18; 0.17; and 0.14 cm, respectively, demonstrating that coir fiber can be utilized as a filler for neutron radiation shielding.

References

Abdullah, M. A. H., Rashid, R. S. M., Amran, M., Hejazii, F., Azreen, N. M., Fediuk, R., … Idris, M. I. (2022, July 1). Recent Trends in Advanced Radiation Shielding Concrete for Construction of Facilities: Materials and Properties. Polymers. MDPI. https://doi.org/10.3390/polym14142830

AbuAlRoos, N. J., Baharul Amin, N. A., & Zainon, R. (2019, December 1). Conventional and new lead-free radiation shielding materials for radiation protection in nuclear medicine: A review. Radiation Physics and Chemistry. Elsevier Ltd. https://doi.org/10.1016/j.radphyschem.2019.108439

Adeli, R., Shirmardi, S. P., & Ahmadi, S. J. (2016). Neutron irradiation tests on B4C/epoxy composite for neutron shielding application and the parameters assay. Radiation Physics and Chemistry, 127, 140–146. https://doi.org/10.1016/j.radphyschem.2016.06.026

Azreen, N. M., Rashid, R. S. M., Haniza, M., Voo, Y. L., & Mugahed Amran, Y. H. (2018). Radiation shielding of ultra-high-performance concrete with silica sand, amang and lead glass. Construction and Building Materials, 172, 370–377. https://doi.org/10.1016/j.conbuildmat.2018.03.243

Chen, S., Bourham, M., & Rabiei, A. (2015). Neutrons attenuation on composite metal foams and hybrid open-cell Al foam. Radiation Physics and Chemistry, 109, 27–39. https://doi.org/10.1016/j.radphyschem.2014.11.003

El-Samrah, M. G., Abdel-Rahman, M. A. E., & El Shazly, R. M. (2018). Effect of heating on physical, mechanical, and nuclear radiation shielding properties of modified concrete mixes. Radiation Physics and Chemistry, 153, 104–110. https://doi.org/10.1016/j.radphyschem.2018.09.018

Erdem, M., Baykara, O., Doĝru, M., & Kuluöztürk, F. (2010). A novel shielding material prepared from solid waste containing lead for gamma ray. Radiation Physics and Chemistry, 79(9), 917–922. https://doi.org/10.1016/j.radphyschem.2010.04.009

Gosset, D., Herter, P., & Motte, V. (2018). Evaluation of damage in neutron irradiated boron carbide. Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms, 434, 66–72. https://doi.org/10.1016/j.nimb.2018.08.021

Kharita, M. H., Takeyeddin, M., Alnassar, M., & Yousef, S. (2008). Development of special radiation shielding concretes using natural local materials and evaluation of their shielding characteristics. Progress in Nuclear Energy, 50(1), 33–36. https://doi.org/10.1016/j.pnucene.2007.10.004

Kurudirek, M. (2017). Heavy metal borate glasses: Potential use for radiation shielding. Journal of Alloys and Compounds, 727, 1227–1236. https://doi.org/10.1016/j.jallcom.2017.08.237

More, C. V., Alsayed, Z., Badawi, M. S., Thabet, A. A., & Pawar, P. P. (2021, June 1). Polymeric composite materials for radiation shielding: a review. Environmental Chemistry Letters. Springer Science and Business Media Deutschland GmbH. https://doi.org/10.1007/s10311-021-01189-9

Naikwadi, A. T., Sharma, B. K., Bhatt, K. D., & Mahanwar, P. A. (2022, March 14). Gamma Radiation Processed Polymeric Materials for High Performance Applications: A Review. Frontiers in Chemistry. Frontiers Media S.A. https://doi.org/10.3389/fchem.2022.837111

Papachristoforou, M., & Papayianni, I. (2018). Radiation shielding and mechanical properties of steel fiber reinforced concrete (SFRC) produced with EAF slag aggregates. Radiation Physics and Chemistry, 149, 26–32. https://doi.org/10.1016/j.radphyschem.2018.03.010

Rajesh, M., & Pitchaimani, J. (2018). Dynamic mechanical and free vibration behavior of natural fiber braided fabric composite: Comparison with conventional and knitted fabric composites. Polymer Composites, 39(7), 2479–2489. https://doi.org/10.1002/pc.24234

Shams, T., Eftekhar, M., & Shirani, A. (2018). Investigation of gamma radiation attenuation in heavy concrete shields containing hematite and barite aggregates in multi-layered and mixed forms. Construction and Building Materials, 182, 35–42. https://doi.org/10.1016/j.conbuildmat.2018.06.032

Tyagi, G., Singhal, A., Routroy, S., Bhunia, D., & Lahoti, M. (2021, February 15). Radiation Shielding Concrete with alternate constituents: An approach to address multiple hazards. Journal of Hazardous Materials. Elsevier B.V. https://doi.org/10.1016/j.jhazmat.2020.124201

Yanyah, A., & Sutanto, H. (2015). Penentuan Nilai Koefisien Serapan Bahan Dan Dosis Radiasi Pada Variasi Kombinasi Kayu Dan Aluminium. Youngster Physics Journal, 4, 87–92.

Zarvianti, E., Fitriyani, D., Surya Bery, W., Khalid Rivai, A., & Sulistioso, dan G. (2017). Karakterisasi Bahan Perisai Radiasi Neutron Ultra High Molecular Weight Polyethyene Dengan Filler Gd2O3 Menggunakan Teknik Radiografi Neutron. Jurnal Ilmu Fisika (JIF), 9, 1–6.