Nuclear Analysis最新文献

Evaluating the health impact of indoor radon concentration in laboratory environments: a focus on lung cancer risk 评价实验室环境中室内氡浓度对健康的影响：以肺癌风险为重点

Nuclear Analysis

Pub Date : 2025-12-17 DOI: 10.1016/j.nucana.2025.100213

Najeba Farhad Salih , Hiwa Mohammad Qadr

This investigation assessed indoor radon concentrations across 11 laboratories using CR-39 solid-state nuclear track detectors to measure alpha particle emissions. Following exposure, detectors were chemically etched in 6.25 N sodium hydroxide solution at 70.0 ± 0.5 °C for 8 h to visualize alpha tracks, which were subsequently examined via optical microscopy. Measurements demonstrated considerable variability in radon levels between laboratories, even among those situated on identical floors. Radon concentrations ranged from 38.99 Bq m⁻³ (Laboratory 11, third floor) to 61.66 Bq m⁻³ (Laboratory 3, ground floor), yielding a mean value of 47.48 Bq m⁻³. Correspondingly, annual effective doses varied from 0.99 mSv y⁻¹ to 1.56 mSv y⁻¹, with an average of 1.20 mSv y⁻¹. These dose estimates remained substantially below ICRP recommended reference range of 3–10 mSv y⁻¹. Excess lifetime cancer risk calculations showed values between 3.786 × 10⁻³ (Laboratory 11) and 5.989 × 10⁻³ (Laboratory 3). A statistically significant variation in radon concentration was also observed across different age groups (P-value <0.001). Critically, all measured concentrations fell below the UNSCEAR safety threshold of 200 Bq m⁻³, confirming that laboratory occupants face negligible health risks from radon exposure. The findings indicate no actionable radon hazards in the studied facilities.

本研究使用CR-39固态核径迹探测器评估了11个实验室的室内氡浓度，以测量α粒子的排放。曝光后，探测器在70.0±0.5°C的6.25 N氢氧化钠溶液中化学蚀刻8小时，以显示α轨迹，随后通过光学显微镜检查。测量结果表明，实验室之间的氡水平有很大差异，即使在同一楼层的实验室之间也是如此。氡浓度从38.99 Bq m−3（三楼11号实验室）到61.66 Bq m−3（一楼3号实验室）不等，平均值为47.48 Bq m−3。相应地，年有效剂量从0.99毫西弗·y - 1到1.56毫西弗·y - 1不等，平均为1.20毫西弗·y - 1。这些剂量估计值仍大大低于ICRP建议的3-10毫西弗/−1参考范围。超额终生癌症风险计算值在3.786 × 10−3（实验室11）和5.989 × 10−3（实验室3）之间。不同年龄组的氡浓度也有统计学上的显著差异（p值<；0.001）。至关重要的是，所有测量的浓度都低于辐射科委会200 Bq m - 3的安全阈值，证实实验室人员因氡暴露而面临的健康风险可以忽略不计。调查结果表明，在所研究的设施中没有可采取行动的氡危害。

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引用次数: 0

Estimating the uranium content in blood samples of healthy and cancer-affected women in the city center of Al-Muthanna governorate, Iraq 估计伊拉克Al-Muthanna省市中心健康和癌症妇女血液样本中的铀含量

Nuclear Analysis

Pub Date : 2025-12-12 DOI: 10.1016/j.nucana.2025.100212

Tuqa Haider Al-Zaalimiu , Anees Ali Al-Hamzawi

Uranium (U) is a heavy metal with chemical toxicity and radiological hazards. Chronic exposure, even at low concentrations, may contribute to serious health risks, including cancer. For this reason, it was necessary to measure the uranium content (UC) in blood samples of two groups of women (healthy and cancer patients) residing in the city center of Al-Muthanna Governorate. The Fission Track Analysis (FTA) technique with a CR-39 detector was applied to evaluate the UC in blood samples. Statistical comparisons between concentrations were performed using an independent t-test (p ≤ 0.05). The result illustrates that the UC in blood samples of the healthy women ranged from (0.74 ± 0.04 to 2.22 ± 0.04) with an average value equal to 1.14 ± 0.06 μg/l. In contrast, the UC for the cancer group ranged from (1.70 ± 0.04 to 4.22 ± 0.06) μg/l, with the mean value equal to 2.93 ± 0.05 μg/l. The findings revealed statistically significant differences (p < 0.001) in UC between the two groups, suggesting a correlation between the incidence of cancer in Iraqi women and elevated levels of UC in their blood. Preliminary observation showed higher UC among women working in the health sector (1.50 μg/l for healthy women and 3.59 μg/l for patients) compared to women in other occupations included in this study. Indicating a potential relationship between occupation type and increased UC. However, this association remains unconfirmed and requires further studies.

铀(U)是一种具有化学毒性和放射性危害的重金属。长期接触，即使浓度很低，也可能造成严重的健康风险，包括癌症。为此，有必要测量居住在Al-Muthanna省市中心的两组妇女（健康妇女和癌症妇女）血液样本中的铀含量。采用裂变径迹分析（FTA）技术和CR-39检测器对血液样品中的UC进行了评价。浓度间比较采用独立t检验（p≤0.05）。结果表明，健康女性血液中UC的变化范围为（0.74±0.04 ~ 2.22±0.04），平均值为1.14±0.06 μg/l。癌症组UC为（1.70±0.04 ~ 4.22±0.06）μg/l，平均值为2.93±0.05 μg/l。研究结果显示，两组之间UC有统计学上的显著差异（p < 0.001），这表明伊拉克妇女的癌症发病率与其血液中UC水平升高之间存在相关性。初步观察显示，与本研究中其他职业的妇女相比，在卫生部门工作的妇女的UC较高（健康妇女为1.50 μg/l，患者为3.59 μg/l）。表明职业类型与UC增加之间存在潜在关系。然而，这种关联尚未得到证实，需要进一步研究。

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引用次数: 0

Determination of gadolinium in leachate by PGNAA PGNAA法测定渗滤液中的钆

Nuclear Analysis

Pub Date : 2025-12-11 DOI: 10.1016/j.nucana.2025.100205

O.V. Chakilev, S.V. Kolesnikov, S.G. Rudakov

The determination of gadolinium in aqueous solution was carried out using a DT portable pulsed neutron generator and a

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7.6 × 7.6 cm

L a B r_{3}

detector. The pulse mode of the acquisition process allows the separation of the registration of radiation capture, inelastic scattering and induced activity. The technique is based on the registration of secondary gamma radiation of the sample from the thermal neutron capture reaction. After correction of the neutron self-absorption effect, the nonlinear response between peak areas and Gd concentrations was converted to a linear response, and calibration curves were used to determine the minimum detection concentration (MDC). Significant improvements in gadolinium detection are achieved, and the MDC of Gd in 300 ml of aqueous solution was 11 ppm.

采用DT便携式脉冲中子发生器和∅7.6 × 7.6 cm LaBr3探测器对水溶液中的钆进行测定。采集过程的脉冲模式允许分离辐射捕获、非弹性散射和诱导活度的登记。该技术是基于从热中子捕获反应的样品的二次伽马辐射的登记。校正中子自吸收效应后，将峰面积与Gd浓度之间的非线性响应转化为线性响应，利用标定曲线确定最小检测浓度（MDC）。在300 ml水溶液中，钆的检测得到了显著的改进，其MDC为11 ppm。

引用次数: 0

Theoretical and experimental validation of dual rhenium radioisotope production for enhanced targeted cancer therapy 双铼放射性同位素生产增强肿瘤靶向治疗的理论和实验验证

Nuclear Analysis

Pub Date : 2025-12-01 DOI: 10.1016/j.nucana.2025.100202

Ranjbar Hassan , Bagheri Reza , Janjani Iman

Objective

For many years, different ligands have been combined with rhenium therapeutic radioisotopes, specifically rhenium-186 and 188, to create radiopharmaceuticals for the treatment of various illnesses. Because of the unique qualities that set each of these radioisotopes apart, they can all be used to eradicate different kinds of cancers. Large cancers can be effectively removed in 188Re thanks to the use of great-energy, long-distance beta particles. However, ¹⁸⁶Re's short range, low energy beta particles are a sufficient weapon to destroy tiny tumors with a high yield and little side effects. As a result, the properties of each of these radioisotopes can only partially address the therapy on their own. Therefore, we reasoned that ¹⁸⁸Re and ¹⁸⁶Re in conjunction must provide the greatest results when treating tumors of different sizes. One possible outcome of neutron-irradiation of natural rhenium is the simultaneous production of ¹⁸⁶Re and ¹⁸⁸Re.

Methods

We want to know if the natural irradiation of rhenium, together with the simultaneous synthesis of these radioisotopes, provides us with the right amounts of radioactivity to make compositional radiopharmaceuticals. This study examines the kind and quantity of impurities created, as well as the practical and theoretical evaluations of the simultaneous generation of ¹⁸⁸Re and ¹⁸⁶R to achieve compositional radiopharmaceuticals by neutron irradiation of natural rhenium in 5MWt pool-type light water research reactor.

Results

The outcomes demonstrated that the theoretical computations and experimental data correlate well. The data's greatest relative error has been determined to be 8 %.

Conclusion

The findings shown that ¹⁸⁶Re and ¹⁸⁸Re could be produced simultaneously with suitable and almost equal activities with irradiating natural rhenium for 100–120 h and considering 24 h for cooling. Also, the levels of impurities in the simultaneous manufacture of ¹⁸⁶Re and ¹⁸⁸Re using the neutron irradiation of natural rhenium are negligible in comparison to the primary products, and the primary products' activities are sufficient to make compositional radiopharmaceuticals.

目的多年来，人们已将不同的配体与铼治疗放射性同位素（特别是铼-186和铼- 188）结合，以制造治疗各种疾病的放射性药物。由于每种放射性同位素的独特特性，它们都可以用来根除不同类型的癌症。在188Re，由于使用了高能、远距离的β粒子，大型肿瘤可以被有效地切除。然而，186Re的短程、低能β粒子是一种足以摧毁微小肿瘤的武器，产量高，副作用小。因此，每一种放射性同位素的特性只能部分地解决它们自己的治疗问题。因此，我们认为188Re和186Re联合使用在治疗不同大小的肿瘤时效果最好。中子辐照天然铼的一个可能结果是同时产生186Re和188Re。方法我们想知道自然照射铼，并同时合成这些放射性同位素，是否为我们提供了适量的放射性来制造放射性药物。本研究考察了在5MWt池式轻水研究堆中，天然铼中子辐照同时生成188Re和186R以获得组份放射性药物的杂质种类和数量，并进行了实践和理论评价。结果理论计算结果与实验数据吻合良好。数据的最大相对误差被确定为8%。结论186Re和188Re可与天然铼辐照100 ~ 120 h，考虑冷却24 h，同时生成，活性适宜且基本相等。此外，与初级产品相比，使用天然铼的中子辐照同时制造186Re和188Re的杂质水平可以忽略不计，初级产品的活性足以制造合成放射性药物。

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引用次数: 0

New arrangements of FAs at BNPP's reactor: PPF and burnup calculations 法国核动力集团反应堆中FAs的新安排：PPF和燃耗计算

Nuclear Analysis

Pub Date : 2025-11-26 DOI: 10.1016/j.nucana.2025.100204

Farhad Zolfagharpour, Zeinab Tayyari-Sadegh

In this work, the two assemblies named 16B36 and 36B20, and two arrangements named B and C, were introduced. The current arrangement of assemblies (named arrangement A) in the core of the BNPP reactor, was changed and the new assemblies were replaced, while the main characteristics of the core were maintained unchanged. The new arrangements and new assemblies were simulated in the MCNPX.2.6.0 code. For each arrangement, some parameters were calculated like: the effective multiplication factor, power peaking factor (PPF), energy deposition, average linear power density, maximum linear heat rate in hot rod, and the burnup after 300 operation days. According to the obtained results, arrangement C was suggested for use in BNPP at the first cycle of reactor operation, because in arrangement C, the burnup increases to about 3.3 GWd/MTU, the linear power density increases about 29 %, and the radial power distribution becomes significantly flattened, while the safety margin, including the maximum heat rate in hot rod, is maintained. The maximum heat rate in the hot rod was 35.95 kw/m which is below the allowed value (44.8 kw/m) reported in FSAR.

本文介绍了16B36和36B20两种组合，以及B和C两种排列方式。BNPP反应堆堆芯中现有的组件排列（命名为排列A）被改变，新的组件被替换，而堆芯的主要特征保持不变。在MCNPX.2.6.0代码中模拟了新的排列和新的程序集。对每种布置方式计算了有效倍增系数、功率峰值因子（PPF）、能量沉积、平均线性功率密度、热棒最大线性热率、运行300 d后燃耗等参数。根据得到的结果，建议在反应堆运行的第一个循环中使用C布置，因为在C布置下，燃耗增加到约3.3 GWd/MTU，线性功率密度增加约29%，径向功率分布变得明显平坦，同时保持了安全余量，包括热棒的最大热率。热棒的最大热速率为35.95 kw/m，低于FSAR报告的允许值（44.8 kw/m）。

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引用次数: 0

Polyvinyl alcohol composites (PVA) with added Pb, Bi, and Sn: A study on radiation shielding and gamma ray attenuation 添加铅、铋和锡的聚乙烯醇复合材料（PVA）的辐射屏蔽和γ射线衰减研究

Nuclear Analysis

Pub Date : 2025-11-24 DOI: 10.1016/j.nucana.2025.100203

Ali K. Al-Muttairi , Norlaili A. Kabir

Lead (Pb) is widely used for radiation shielding due to its high atomic number, density, affordability, and availability. However, its toxicity poses serious environmental and health risks. This study aims to evaluate the gamma-ray shielding performance of polyvinyl alcohol (PVA)-based shielding composites in the attenuation of ⁶⁰Co, ¹³⁷Cs, and ²⁴¹Am sources. A PVA-based shielding material incorporating Pb, Bi₂O₃, and Sn were evaluated for its radiation attenuation properties, using Pb as the benchmark standard for comparison of shielding effectiveness. PVA was selected for its hydrophilicity, ease of mixing, and light-weight property. A total of 18 shielding samples were fabricated, with six samples for each metal. The variables include metal percentages of 10 %, 20 %, and 30 %, as well as thicknesses of 0.6, 0.8, and 1.0 cm. Pb composites showed the highest attenuation among all samples, while Bi₂O₃ and Sn composites also demonstrated strong shielding performance. The results showed that increasing the metal percentage per unit thickness has a much greater effect on shielding performance than simply increasing thickness. Increasing metal percentage at constant thickness significantly increases both linear and mass attenuation coefficients for all samples while reducing their HVL. At a constant thickness of 0.8 cm, increasing the metal composition from 10 % to 30 % results in a rise in the linear attenuation coefficient. For PVA/Pb, it increases from 1.75 cm⁻¹ to 2.7 cm⁻¹, for PVA/Bi₂O₃, from 1.8 cm⁻¹ to 1.9 cm⁻¹, and for PVA/Sn, from 1.3 cm⁻¹ to 1.5 cm⁻¹. In summary, optimal shielding efficiency is primarily determined by the metal percentage per unit thickness, as photon attenuation depends more on the concentration of heavy atoms along the radiation path than on overall shielding thickness.

铅（Pb）由于其高原子序数、密度、可负担性和可用性而被广泛用于辐射屏蔽。然而，它的毒性造成了严重的环境和健康风险。本研究旨在评价聚乙烯醇（PVA）基屏蔽复合材料对60Co、137Cs和241Am源的屏蔽性能。以Pb作为屏蔽效果的基准标准，对含Pb、Bi2O3和Sn的pva基屏蔽材料的辐射衰减性能进行了评价。选择PVA是因为它的亲水性、易于混合和重量轻。共制作了18个屏蔽试样，每种金属6个试样。这些变量包括10%、20%和30%的金属百分比，以及0.6、0.8和1.0厘米的厚度。Pb复合材料的屏蔽性能最高，Bi2O3和Sn复合材料也表现出较强的屏蔽性能。结果表明，增加单位厚度金属含量对屏蔽性能的影响远大于单纯增加厚度。在厚度不变的情况下，增加金属含量显著增加了所有样品的线性衰减系数和质量衰减系数，同时降低了它们的HVL。当厚度为0.8 cm时，将金属成分从10%增加到30%会导致线性衰减系数上升。PVA/Pb从1.75 cm−1增加到2.7 cm−1，PVA/Bi2O3从1.8 cm−1增加到1.9 cm−1，PVA/Sn从1.3 cm−1增加到1.5 cm−1。综上所述，最佳屏蔽效率主要取决于每单位厚度的金属百分比，因为光子衰减更多地取决于沿辐射路径的重原子浓度，而不是总体屏蔽厚度。

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引用次数: 0

Activity levels and radiological hazards of chemical fertilizers used for farm crops in Ondo city, Southwest, Nigeria 尼日利亚西南部翁多市用于农作物的化学肥料的活动水平和放射性危害

Nuclear Analysis

Pub Date : 2025-10-26 DOI: 10.1016/j.nucana.2025.100201

Lasun Tunde Ogundele , Muyiwa Micheal Orosun , Similoluwa Akiniran , Patrick Oluwagbemiga Ayeku

Fertilizers contain several radioactive elements of the decay series of ²³⁸U, ²²⁶Ra and ²³²Th and they can be a source of human exposure to gamma radiation when crops grown with fertilizers are consumed by human. The activity concentrations of ²³⁸U, ²³²Th and ⁴⁰K in three brands of fertilizers were measured using gamma-ray spectrometry and the radiological indices [Radium Equivalent activity (Ra_eq), Absorbed Dose rate (DR), Annual Effective Dose rate (AED), External hazard (H_ex), and Internal hazard (H_in)] were estimated. The average activity concentrations of ²³⁸U, ²³²Th and ⁴⁰K were 4.98 ± 1.71, 12.35 ± 2.45 and 11.89.05 ± 288.91 Bqkg⁻¹; 7.50 ± 1.84, 16.60 ± 3.32 and 2080.72 ± 251.25 Bqkg⁻¹ and 2.46 ± 0.68, 5.96 ± 1.24 and 306.82 ± 70.46 Bqkg⁻¹ for NPK 15-15-15, NPK 15-15-17 and Urea, respectively. The values of radiological indices were lower than the permissible limits stipulated by world average values except Ra_eq and absorbed dose rate. Therefore, it can be concluded that no significant radiological health risk occurs. However, the presence of radionuclides in the fertilizers could be an exposure pathway that gamma radiation enters the food chain and threaten food production with deleterious health implications on the consumers of the such crops.

肥料含有238U、226Ra和232Th衰变系列的几种放射性元素，当人类食用用肥料种植的作物时，它们可能成为人类暴露于伽马射线的来源。采用γ射线能谱法测定了3种化肥中238U、232Th和40K的活性浓度，并估算了放射性指标[镭当量活度（Raeq）、吸收剂量率（DR）、年有效剂量率（AED）、外危害（Hex）和内危害（Hin）]。238U、232Th和40K的平均活性浓度分别为4.98±1.71、12.35±2.45和11.89.05±288.91 Bqkg−1；NPK 15-15-15、NPK 15-15-17和尿素分别为7.50±1.84、16.60±3.32和2080.72±251.25 Bqkg -1和2.46±0.68、5.96±1.24和306.82±70.46 Bqkg -1。除Raeq和吸收剂量率外，其他放射学指标均低于世界平均值规定的允许限值。因此，可以得出结论，没有发生重大的放射性健康风险。然而，肥料中放射性核素的存在可能是伽马辐射进入食物链的暴露途径，威胁粮食生产，对这类作物的消费者产生有害的健康影响。

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引用次数: 0

Benchmarking of the efficiency of the NaI(Tl) detector using FLUKA, MCNP, and experimental measurements at multiple source distances 使用FLUKA、MCNP和多源距离的实验测量对NaI（Tl）检测器的效率进行基准测试

Nuclear Analysis

Pub Date : 2025-10-15 DOI: 10.1016/j.nucana.2025.100185

Zeenat Ullah , Abdelhamid Jalil , Xianpeng Yin , Yingming Sang , Javed Hussain , Muhammad Shoaib , Ghulam Hussan , Da Chen

Accurate calibration of NaI(Tl) scintillation detectors is essential for reliable gamma-ray spectrometry in nuclear safeguards and environmental radiation monitoring. This study investigates the full energy peak efficiency (FEPE) of a

2^{''} \times 2^{''}

NaI(Tl) detector using experimental measurements and Monte Carlo simulation performed with FLUKA and MCNP. Standard point sources (

^{133} Ba

,

^{137} Cs

, and

^{60} Co

) were measured at four source-detector distances (4, 8, 12, and 16 cm) covering photon energies from 356 to 1333 keV. Both simulation tools demonstrated an average deviation of less than 6 % and a maximum deviation of 18 % from the experimental results in all configurations. Furthermore, source misalignment was numerically evaluated and found to have a measurable impact only at short source-detector distance. This work represents the first integrated benchmarking of FLUKA and MCNP against experimental FEPE data across multiple geometries, offering a validated framework for accurate detector modeling and calibration.

NaI（Tl）闪烁探测器的精确校准对于核保障和环境辐射监测中可靠的伽马射线能谱至关重要。本研究利用FLUKA和MCNP进行的实验测量和蒙特卡罗模拟，研究了2“×2”NaI（Tl）探测器的全能量峰值效率（FEPE）。标准点源（133Ba， 137Cs和60Co）在四个源-探测器距离（4,8,12和16 cm）测量，光子能量从356到1333 keV。两种模拟工具在所有配置下与实验结果的平均偏差小于6%，最大偏差为18%。此外，对源不对中进行了数值评估，发现只有在源-探测器距离较短时才会产生可测量的影响。这项工作代表了FLUKA和MCNP首次针对多种几何形状的实验FEPE数据进行综合基准测试，为精确的探测器建模和校准提供了一个经过验证的框架。

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引用次数: 0

Monte Carlo simulation of dose and residual activation in a polyethylene shuttle of the TRIGA Mark II reactor TRIGA Mark II反应器聚乙烯梭体的剂量和残余活化的蒙特卡罗模拟

Nuclear Analysis

Pub Date : 2025-10-14 DOI: 10.1016/j.nucana.2025.100200

Khalid Nabaoui , Abdessamad Didi , El Mehdi Alibrahmi , Otmane Allaoui , Jamila Yousfi , El Mahjoub Chakir

This study focuses on the use of polyethylene as the primary material for the fabrication of an irradiation shuttle intended for the TRIGA Mark II reactor. Designed to accommodate multiple sample capsules, the shuttle is subjected to prolonged neutron irradiation under real operating conditions. The objective is to analyze the interactions between thermal neutrons and polymeric materials in order to better understand their structural and radiological behavior under irradiation. The dose distribution was numerically modeled using the PHITS code, enabling precise identification of the regions of maximum intensity within the shuttle. The results provide a basis for optimizing the materials employed in nuclear environments, integrating radiological safety requirements with durability and mechanical performance.

本研究的重点是使用聚乙烯作为制造用于TRIGA Mark II反应堆的辐照梭的主要材料。设计用于容纳多个样品胶囊，航天飞机在实际操作条件下受到长时间的中子辐照。目的是分析热中子与高分子材料之间的相互作用，以便更好地了解它们在辐照下的结构和放射行为。使用PHITS代码对剂量分布进行了数值模拟，从而能够精确识别航天飞机内最大强度的区域。研究结果为优化核环境中使用的材料提供了基础，将放射性安全要求与耐久性和机械性能相结合。

引用次数: 0

Nano-sisal fiber reinforced polymer composites for biocompatible lightweight structural applications 纳米剑麻纤维增强聚合物复合材料的生物相容性轻量化结构应用

Nuclear Analysis

Pub Date : 2025-10-14 DOI: 10.1016/j.nucana.2025.100199

V. Muthukumar , D. Elil Raja , P. Jayaprakash , A. Suresh Babu

This research focuses on the mechanical and thermal characterization of nano-sisal fiber-reinforced polymer composites, exploring the potential of incorporating nanomaterials to enhance the performance of traditional sisal fiber composites. Natural sisal fibers (NSF) serve as the starting point for the chemical and physical processes that produce sisal fibers. Several analytical techniques are used to describe the materials, such as Fourier transform infrared spectroscopy (FTIR), scanning electron microscopy (SEM), high-resolution transmission electron microscopy (HR-TEM), and field emission scanning electron microscopy (FE-SEM). This study investigates the synergistic effects of integrating nanoscale reinforcements into sisal fiber-reinforced polymer matrices. Mechanical properties, including tensile strength, flexural strength, and impact resistance, are systematically evaluated using standardized testing procedures. Fabricating epoxy polymer-based composites involves adding silver fibers in various weight percentages (1, 2, 3, 4, 5, 6, 7, and 8 %). The results highlight the influence of nanoscale additives on the overall mechanical performance and thermal stability of the composite materials. Furthermore, the study investigates the potential for improved load-bearing capacity, durability, flexural strength, tensile strength, impact resistance, thermal analysis, and heat resistance in sisal fiber composite samples, where these composites could exhibit utility. The findings of this research contribute to the understanding of nano-sisal fiber-reinforced polymer composites and their viability in various engineering applications.

本研究重点研究纳米剑麻纤维增强聚合物复合材料的力学和热特性，探索加入纳米材料提高传统剑麻纤维复合材料性能的潜力。天然剑麻纤维（NSF）是生产剑麻纤维的化学和物理过程的起点。几种分析技术用于描述材料，如傅里叶变换红外光谱（FTIR），扫描电子显微镜（SEM），高分辨率透射电子显微镜（HR-TEM）和场发射扫描电子显微镜（FE-SEM）。本研究探讨了将纳米级增强材料整合到剑麻纤维增强聚合物基体中的协同效应。机械性能，包括拉伸强度、弯曲强度和抗冲击性，使用标准化测试程序进行系统评估。制造环氧聚合物基复合材料涉及以不同重量百分比（1、2、3、4、5、6、7和8%）添加银纤维。研究结果强调了纳米级添加剂对复合材料整体力学性能和热稳定性的影响。此外，该研究还调查了剑麻纤维复合材料样品在提高承载能力、耐久性、弯曲强度、拉伸强度、抗冲击性、热分析和耐热性方面的潜力，这些复合材料可以在这些方面展示实用性。本研究结果有助于了解纳米剑麻纤维增强聚合物复合材料及其在各种工程应用中的可行性。

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引用次数: 0