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Jurnal Riset Teknologi Pencegahan Pencemaran IndustriJurnal Riset Teknologi Pencegahan Pencemaran IndustriResearch 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-1, 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. The results of this study can add new information regarding the development of radiation protection systems with new materials that can minimize the bodys exposure to ionizing radiation in the future.
Based on the testing and analysis of coir fiber as a filler in neutron radiation shields, it can be concluded that coir fiber is a natural fiber that can serve as an alternative material for neutron radiation absorption.The absorption capacity of composite boards at fiber mass fractions of 2.3% with linear attenuation coefficient (µ) for each coil fiber fraction is 3.The greater the mass fraction of coir fiber in the radiation shield, the more effective it becomes at absorbing neutron radiation.
Penelitian lebih lanjut dapat dilakukan untuk menguji efektivitas coir fiber composite board dalam melindungi terhadap berbagai jenis radiasi, tidak hanya neutron, tetapi juga gamma dan alfa. Hal ini penting untuk memahami kinerja material secara komprehensif dalam berbagai skenario paparan radiasi. Selain itu, studi perlu dilakukan untuk mengoptimalkan komposisi coir fiber composite board, misalnya dengan menambahkan material lain seperti boron atau litium, yang dikenal memiliki kemampuan menyerap neutron yang tinggi, untuk meningkatkan efisiensi perlindungan radiasi. Terakhir, penelitian perlu difokuskan pada pengembangan metode fabrikasi yang lebih efisien dan ramah lingkungan untuk coir fiber composite board, termasuk eksplorasi penggunaan resin bio-based sebagai pengganti resin polyester konvensional, guna menciptakan material yang berkelanjutan dan ekonomis untuk aplikasi perlindungan radiasi di masa depan. Penelitian-penelitian ini diharapkan dapat memberikan kontribusi signifikan dalam pengembangan sistem perlindungan radiasi yang lebih efektif, aman, dan berkelanjutan.
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