Experimental investigation for radiation shielding performance of B2O3-TeO2-Bi2O3-ZnO-CaO glass system

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2025-02-17 DOI:10.1016/j.anucene.2025.111276
Aljawhara H. Almuqrin , M.I Sayyed , M. Elsafi
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Abstract

This work investigated the gamma-ray attenuation capability of four glass compositions labeled as BTBZC-1, BTBZC-2, BTBZC-3 and BTBZC-4, with fixed amount of Bi2O3 and TeO2 (5 and 20 mol%, respectively), while the CaO and B2O3 decrease from 17 to 8 mol% (in 3 mol% decrement) and 38 to 32 mol% (in 2 mol% decrement), and the ZnO increases from 20 to 35 mol% (in 5 mol% increment). The data was evaluated experimentally using narrow beam method by different point sources and semiconductor detector (HPGe-detector). Experimental data are compared with theoretical predictions (Phy-X software), demonstrating strong agreement with R2 values of 1. The LAC at 0.059 MeV is in the 12.332–13.146 cm−1 range, decreasing at 0.662 MeV to 0.331–0.345 cm−1, thus revealing the prepared glasses to exhibit high shielding efficiency at low energies, primarily due to the photoelectric effect’s dominance, while Compton scattering at higher energies leads to reduced attenuation. The addition of ZnO improves the shielding performance by increasing glass density and Zeff, as confirmed by lower HVL, TVL, and MFP values. The investigation highlights these glasses’ potential for radiation protection, with BTBZC-4 exhibiting superior performance due to its higher ZnO content.
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B2O3-TeO2-Bi2O3-ZnO-CaO玻璃体系辐射屏蔽性能的实验研究
本文研究了在Bi2O3和TeO2分别为5%和20% mol%的情况下,四种标记为BTBZC-1、BTBZC-2、BTBZC-3和BTBZC-4的玻璃组分的γ射线衰减能力,CaO和B2O3分别从17%减少到8mol %(减少3 mol%)和38%减少到32mol %(减少2 mol%), ZnO从20%增加到35mol %(增加5 mol%)。采用窄光束法,利用不同的点源和半导体探测器(hpge探测器)对实验数据进行了评价。实验数据与理论预测(Phy-X软件)进行了比较,结果表明R2值为1。0.059 MeV时LAC在12.332 ~ 13.146 cm−1范围内,0.662 MeV时LAC下降至0.331 ~ 0.345 cm−1,说明制备的玻璃在低能量下具有较高的屏蔽效率,这主要是由于光电效应占主导地位,而高能量下的康普顿散射导致衰减减小。通过降低HVL、TVL和MFP值,ZnO的加入提高了玻璃密度和Zeff,从而改善了屏蔽性能。该研究强调了这些玻璃的辐射防护潜力,BTBZC-4由于其较高的ZnO含量而表现出优异的性能。
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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