Radiation Protection Properties Research Articles

Effect of tin oxide particle size on epoxy resin to form new composites against gamma radiation.

The aim of the present study is to assess the shielding performance of a novel lead-free epoxide material against ionizing radiation. The effect of variation in particle size and concentration of tin oxide (SnO), which was added to epoxy resin polymer (ER), on its radiation shielding properties has been investigated in this research. Ten samples of ER samples incorporated with different concentrations (0%,20%,40%,60%) of SnO microparticles, nanoparticles, and both sizes combined were prepared and assessed. The linear attenuation coefficients (LAC) were measured experimentally through the collimated gamma-ray beam at 0.0595MeV, 0.6617MeV, 1.1730MeV, and 1.330MeV emitted from Am-241, Cs-137 and Co-60, respectively (to cover all energy range of gamma rays) for all samples with various concentrations and particle sizes of SnO. The other radiological shielding parameters such as half value layer (HVL), tenth value layer (TVL), and radiation protection efficiency (RPE) were estimated and compared for all different samples. The results prove that the increasing of the concentration and reducing the particle size of SnO leads to the enhancement of the radiation protection properties of the ER polymer. Moreover, it was observed that the incorporation of SnO micro- and nanoparticles together improves the radiation shielding properties of ER samples. Conclusively, the reinforcing of ER polymer material matrix by micro/nanoparticles of SnO as composite with enhanced radiation shielding specifications was highlighted.

Self-adhesive elastic radiation protective coatings

Elastic self-adhesive radiation protective coatings with high adhesive strength to various substrates have been developed and can be applied to surfaces of any shape. In terms of radiation protection properties, they surpass foreign analogues by 15–35% barite-containing at an energy of 0.059 MeV, by 8%, 30% and even 200% tungsten-containing at an energy of 0.661 MeV. In terms of cost, tungsten-containing materials are 2–3 times cheaper than foreign analogues, and barite materials are 67–109 times cheaper than foreign analogues, and 2–3.5 times cheaper than domestic ones. With an absorbed radiation dose of 2.62.107 Gy (threshold value of 105 Gy), they retain radiation-protective properties and have minor damage.

Bioinspired Three-Component System to Prepare Full-Color Functional Biomimetic Pigments.

Nature provides a great source of inspiration for the development of sustainable materials with excellent properties, among which melanin with optical, electronic, and radiation protection properties are considered to be promising coloring materials. However, compared to chemical pigments, the single color, complex oxidation process, and poor solubility of natural melanin strongly limit their further applications. Here, we introduce a series of melanin-like polymeric pigments with amino acid-encoded physicochemical properties by a simple three-component reaction system. Our protocol enables artificial control of the chromophore structures through the rational design of the substrates and dopants, thereby combining the safety and functionality of biopigments with the color richness of chemical dyes. Similar to the photoprotective effect of natural melanin, the polymeric pigments showed excellent antioxidant activity in reducing free radicals and have the advantages of iridescent color, strong tinting strength, stability, and affordability. Furthermore, due to their ability to dye substrates, these biomimetic are expected to become new low-cost bioactive chromophores and find various biochemical applications such as in clothing and hair dyeing, food addition, and anticounterfeiting detection.

BaTiO3-B2O3-MgO-Na2O-CaO glass series: Radiation shielding, thermal, and mechanical properties

The effect of BaTiO3 on the mechanical, thermal and radiation shielding properties of the borate glass with the composition of (60-x)B2O3 + 10MgO + 15Na2O + 15CaO+(x)BaTiO3 (x: 0,2.5,5,7.5 and 10 mol%) were synthesized by the melt quenching method. The physical, thermal, mechanical and radiation protection properties of the glasses produced with this designed composition were carefully investigated. As the BaTiO3 amount increased from 0 % to 10 %, the density of the glass increased from 2.571 to 2.870 g/cm3 and the glass thermal stability (ΔT) also enhanced from 51 to 63. The LAC value at 276 keV, 0.2831 cm−1 for 0 % BaTiO3 and enhanced linearly with increasing BaTiO3 concentration and reach to 0.3475 cm−1 at 10 % BaTiO3. The experimentally obtained MAC values are in agreement with the theoretically calculated MAC values with XCOM and MCNP6.2. It was concluded that the increase in the BaTiO3 value of the glass positively affects the radiation shielding properties of the glasses.

Composite based on Poly(ethylene-co-vinyl acetate) with lead-titanate for gamma attenuation

The radioprotective ability of composite materials based on a poly (ethylene-co-vinyl acetate) matrix with dispersed lead titanate filler has been estimated. The filler was obtained from the environmentally friendly synthesis based on exchanging potassium ions for lead in potassium titanates. The gamma ray protective composites have low density, good mechanical qualities and are able to be reprocessed by high-performance extrusion or injection molding techniques. The present work is dedicated to assess mechanical and gamma ray shielding properties of poly (ethylene-vinyl acetate) composites with different lead titanate content (70, 80 and 90 wt percent of lead titanate). The study was carried out for the emission of 137Cs, 60Co and 241Am isotopes with energies 0.6617 MeV, 1.332/1.173 MeV and 0.0595 MeV respectively. The study of radiation-protective properties showed that for 137Cs radiation half value layer for the composite containing 90 wt% of lead titanate is three times higher than for neat lead: 2.1 and 0.7 cm respectively. For the 60Co emission, these values are more close: 1.9 cm for 90 wt% composite and 1.2 cm for lead. The layer of 0.5 cm of composite with 70 % lead titanate almost fully diminishes the low-energetic 241Am radiation, and hence, is superior to lead foil of the same length. Mass attenuation coefficients of 70% composite for 0.6617 MeV, 1.332/1.173 MeV and 0.0595 MeV are 0.088, 0.046 and 2.487 cm2/g respectively. The tensile elongation at fracture decrease is 460% for 70/30 lead titanate/poly (ethylene-vinyl acetate) and is equal to 6% for 90/10 lead titanate/poly (ethylene-vinyl acetate).

Radiation shielding, optical, structural, morphological, and thermal features for tellurite glass ceramics

A new series of tellurite glass-ceramic was prepared for potential utilization in the radiation shielding field. The thermal features of parent glasses were assessed to choose the best heat treatment technique. The morphological and structural properties of glass ceramics were investigated by scanning electron microscope (SEM), X-ray diffraction (XRD), and Fourier transform infrared (FTIR). The UV absorption was utilized to calculate the optical features of glass ceramics. The shielding properties were computed based on the Phy-X software. The transformation of glasses to glass ceramics enhanced the density of all glass ceramics. XRD results exhibited an orthorhombic BaTeO3 crystalline phase for the TMSB0 and TMSB5 samples. It is proved that the monoclinic molybdenum tellurium oxide (Mo5TeO16) crystalline phase for TMSB10, TMSB15, and TMSB20 samples. Also, the change in crystalline phase resulted from adding MoO3 instead of TeO2. SEM results affirmed the role of MoO3 in improving the structure of glass ceramics. The thermal stability and weight loss of TMSB20 samples are higher than other glasses. Also, the adding MoO3 led to a slight enhancement in the radiation shielding properties of the prepared samples. Data indicate that adding MoO3 to the glasses enhanced the glass-ceramic samples' thermal, structural, and radiation protection properties.

Investigation of gamma radiation shielding and antimicrobial properties of PbO-doped ZnO and TiO2 composites

Gamma radiation is utilized in various fields, such as food shelf-life preservation, medicine, and industry. The protection against ionizing radiation, such as gamma radiation, is a crucial matter. Ionizing radiation is harmful to both the environment and living organisms, leading to cellular mutations, organ damage, equipment malfunctions, and other adverse effects. To achieve radiation protection, shielding methods are employed. Materials that prevent bacterial growth and contamination should also be developed in all areas. In our study, glass substrates were coated using the rotational coating method. In this study, the antimicrobial and radiation protection properties of glass coatings prepared with ZnPb (50% ZnO + 50% PbO) and TiPb (50% TiO2 + 50% PbO) ratios were investigated. For radiation protection properties, mass attenuation coefficient (MAC) values were calculated using the Geant4-GATE and XCOM simulations, and the results were compared with the experimental data. Calculations were performed at 511, 662, 1173, 1274, and 1332 keV energy levels. A colony counting method was employed to determine the antibacterial effectiveness of Pb-doped TiO2 and ZnO. The antibacterial efficacy of Pb-doped TiO2 and ZnO films was tested against Staphylococcus aureus (ATCC 25923) and Escherichia coli (ATCC 25922) bacteria. It was found that these films were effective only against Staphylococcus aureus bacteria. The antimicrobial efficiency of the nanocomposites was evaluated against various bacterial strains, highlighting significant inhibitory properties, particularly for TiO2 and ZnO nanocomposites against S. aureus. This emphasizes their potential as antimicrobial agents.

Comparative Study of Biosynthesizing Selenium Nanoparticles by Gum Arabic and Poly Anionic Cellulose to Prevent Radiation-Induced Death in Chinese Hamster Ovary (CHO) Cells

Purpose: In premenopausal women, abdominopelvic radiotherapy may have a direct and profound effect on ovarian function. Stabilized selenium Nanoparticles (NPs) with some natural materials have been demonstrated to have high antioxidant activity and reduce radiation damage as a radioprotector. This study was done to compare the ability for the biosynthesis of selenium NPs by Gum Arabic (Se-GA) and Polyanionic Cellulose (Se-PAC) in the protection of Chinese Hamster Ovary (CHO) cells against radiation damage.
 Materials and Methods: First, Selenium Nanoparticles (SeNPs) were synthesized in the presence of GA and PAC. Then, CHO cells were cultured in-vitro and were randomly divided into six groups in different concentrations of Se-GA and Se-PAC to measure the biocompatibility of NPs. Finally, cells were treated with NPs and radiation (6MV, 2Gy), and the percentage of cell survival was determined by MTT assay. Both NPs with an average size of 20-30 nm and an absorption absorbance peak at about 300 nm using Ultraviolet-Visible (UV–Vis) spectroscopy.
 Results: According to the parametric t-test analysis, Se-GA nanoparticles with a concentration higher than 0.4 ppm significantly increased the radioprotective effect on CHO cells compared to the control group (P<0.05). However, Se-PAC showed no significant increase in radioprotection in contrast to the control group (P>0.05).
 Conclusion: Se-GA nanoparticles have antioxidant properties, and the radiation protection properties of Se-GA nanoparticles are significantly higher than control. Consequently, Se-GA nanoparticles showed promising results and may be able to play the role of a radioprotector.

Обеспечение безопасного контроля радиационно-защитных свойств спецодежды пожарных

The radiation-protective clothes production to equip firefighters guarding nuclear power plants has been established in Russia. Special protective clothes were designed at the Institute for Nuclear Research of the Russian Academy of Sciences under the supervision of Boris Benetsky (1933–2015). According to the state standard GOST R 53264—2019, the radiation-protective properties of special protective clothes are tested with gamma and beta rays in accordance with the methodology developed at the Institute for Nuclear Research of the Russian Academy of Sciences, which ensures the radiation safety of the test. It is required to check the decontamination coefficient; however, this testing method is still hazardous due to the use of open-type radiation-hazardous substances. To ensure the safety of the test, the simulation method has been proposed based on the substitution of the hazardous substance with a safe dust-like pollutant, whereas the decontamination is to be assessed by the adhesion index. The adhesive tape method to assess the contamination of the surface is used. Two casts are taken from two sections of the tested surface before and after the treatment with a detergent. The images of the casts are converted into digital form via a scanner and then computer-processed by the specially designed GLASS application. The contamination of the casts depends on the amount of dust stuck. Upon the determination of the average contamination of each cast, data is obtained to calculate the adhesion index. The result of the test of the same material by simulation method differs from the standard method by 20 %.

Synthesis and characterizations of Ce-doped ZnO thin films for radiation shielding

In this research, different amounts of Ce-doped ZnO thin films were synthesized using the spray pyrolysis method. Structural, morphological and optical properties of these synthesized films were investigated. In XRD analyses, wurtzite (hexagonal) structures were observed in the films. In SEM analysis, there were changes in the surface morphology of the films with doping, and in cross-section measurement, the thickness of the films was measured to be approximately 1.2 μm. In UV–vis spectrometry analysis, it is seen that the effect of Cerium contribution on optical transmittance and band gap positively affects shielding. NaI(Tl) detector and gamma energies of 384, 1173, and 1333 keV have been used to investigate the radiation protection properties of these synthesized films. As a result of these measurements, linear attenuation coefficient (LAC) values have been obtained. Radiation shielding parameters have been calculated with these (LAC) values. The Mass Attenuation Coefficient (MAC), Half Value Layer (HVL), Tenth Value Layer TVL (and) Mean Free Path (MFP) values have been also calculated using this LAC result. According to these results, Ce-doped ZnO films were found to be effective in radiation shielding.

Mechanical properties, attenuation coefficient, and microstructure of ultra high-performance heavyweight concrete for radiation shielding applications

This paper explores the characteristics of ultra-high-performance heavyweight radiation shielding concrete by using many types of radiation-resistant aggregates. The experimental work is carried out in two groups, The first group contains six mixes that are prepared by using barite, basalt, and serpentine as heavyweight coarse aggregate, and the second group contains six mixes that are prepared by using the same percentages of coarse aggregate in the first group while partially replacing the fine aggregates with hematite. The main research aim is to study radiation absorption characteristics using 60Co sources that discharge 1.25 MeV photons. Linear attenuation coefficient, half-layer value, and tenth-layer value layers were assessed as radiation absorption characteristics. In addition, the hardened characteristics of all mixes like compressive, tensile, flexural strengths, and modulus of elasticity have been investigated, also, microstructure has been tested. Based on the results, The density of mixtures ranged between 2690 and 3080 kg/m3. The largest value of concrete density was recorded for barite with hematite. Although basalt with hematite gave the maximum compressive strength value of 155.8 MPa. Barite with hematite improved the radiation protection properties compared to basalt with sand by 20 % as the Linear attenuation, HVL, and TVL values became 0.173 cm−1, 4.01 cm, and 13.28 cm respectively.

Properties of cement Portland composite prepared with Barium sulfate and Bismuth oxide for radiation shielding

Radiation is useful but can be harmful to humans if used carelessly. Therefore, radiation protection equipment is necessary for workers. In this paper, we aim to study a cement composite with BaSO4/Bi2O3 for protection against X-rays and gamma rays. The shielding ability was measured using a diagnostic X-ray with energies of 60–120 keV and gamma rays of Cs-137, Ba-133, Co-57 and the morphology structure was determined including radiation protection properties. The results showed that Portland cement with a high concentration of BaSO4/Bi2O3 had the ability to absorb radiation from X-rays in the range of 95.54–99.87% and gamma energy in the range of 93.37–98.88%. Moreover, the composite of BaSO4/Bi2O3 induced a homogenous structure of Portland cement possibly affecting the strength of the material. In addition, Portland shielding can be designed for use in related applications in various energy ranges including ones that are environmentally friendly and suitable for the development of radiation protection in the future.

MECHANISM FOR CREATING A CEMENT COMPOSITE WITH ENHANCED HYDROPHYSICAL AND RADIATION PROTECTION PROPERTIES

In modern conditions, the environmental component of building protective materials is guaranteed by the creation of composites capable of protecting underground and above-ground parts of buildings and structures in flooded areas from the filtration of radiation-contaminated water, industrial wastewater, radon, etc. Therefore, the problem of developing modern, including radiation-protective materials for the construction industry is urgent. Concrete is a good moderator and absorber of fast neutrons and intensively absorbs gamma radiation. Concrete consists of cement, sand and gravel. Cement consists mainly of oxides of various elements (Ca, Si, Al, Fe) and contains light elements. Portland cements, slag Portland cements and alumina cements are used as binders for the preparation of particularly heavy protective concrete. In special concretes, the most effective binder can be a substance that, as a result of hardening, adds a large amount of water (to increase the hydrogen content of the concrete). Such a substance is calcium hydrosulfoaluminate. Recent studies have shown that very effective radiation protection materials are materials in the form of polydisperse systems containing ultrafine particles (UFP) less than 1 micron in size. However, the difficulty is to distribute the ultrafine particles evenly throughout the material volume, which dramatically reduces its protective functions.The work resulted in the development of a cement composite with enhanced hydrophysical and radiation protection properties, which were achieved by, firstly, modifying the cement binder with chemical additives that facilitated the synthesis of crystalline hydrates with a high water content. Secondly, polydisperse systems in the form of ferruginous quartzite were added to the composition, where micron-sized iron particles were embedded in quartzite, which contributed to the uniform distribution of micron-sized iron particles in the volume of the composite. Physicochemical studies of cement stone hydration products were carried out by X-ray diffraction, differential thermal and electron microscopic analyses. The developed composition of fine-grained concrete has high performance and hydrophysical properties, provides protective properties against radiation due to components containing heavy and light atoms, which may allow the use of this material to protect building structures, buildings and structures.

Green synthesis of ZnO nanoparticles decorating electrospun PAN nanofibers for enhanced radiation shielding

A comprehensive examination was conducted in our study regarding the incorporation of zinc oxide (ZnO) nanoparticles into polyacrylonitrile (PAN) nanofibers to improve their radiation protection properties. Using the electrospinning technique, ZnO nanoparticles that were synthesized via the environmentally benign ascorbic acid method were subsequently applied to PAN nanofibers. A multitude of coefficients, including the natural attenuation coefficient and mass attenuation coefficient, are pivotal in evaluating the efficacy of composite materials with regard to radiation protection. It was subjected to a comprehensive evaluation that considered a number of crucial factors: The incorporation of ZnO nanoparticles into PAN nanofiber composites leads to a substantial augmentation in the mass attenuation coefficient, which surges from 0.185 cm2/g to 0.221 cm2/g when compared to pure PAN nanofibers. Similarly, the coefficient of linear attenuation rises from 0.284 1/cm to 0.320 1/cm.

Flexible lightweight Bi2O3-rubber based materials for X-ray protection

The flexible X-ray protective materials are commonly made of lead rubber. They have heavy weight, high biological toxicity, poor flexibility and aging resistance. The "weak absorption zone" in the energy range of 40–88 keV threaten environmental safety and human health. Bi2O3-rubber based flexible X-ray protective materials were prepared by rubber production process. The micromorphology, shore hardness, specific gravity, mechanical properties and radiation protective properties were characterized and analyzed. The results showed that Bi2O3 particles dispersed in natural rubber (R) matrix uniformly. The shore hardness of samples fluctuated between 41° and 46° with the increasing Bi2O3 content, lower than the Level 1 index requirement of the hardness (≤80°) of lead-free composite protective materials. The specific gravity increased from 1.35 g/cm3 to 2.38 g/cm3, which reduced approximately 34% comparing with the commercial protective materials containing Pb. The breaking strength and breaking elongation meet the index requirements in National standard GB 16757-2016. When Bi2O3 content reached 300 parts, the highest lead equivalent and maximum shielding ratio were 0.3012 mmPb and 52.95% respectively. It meets the index requirement of lead equivalent of 0.25 mmPb≤Pb≤0.35 mmPb for the front sheet of protective clothing. The effective shielding range of the protective material R/Bi2O3(100/300) was mainly in the range of incident energy of 65∼100 keV and 164–250 keV, which covered the “weak absorption zone” of lead.

Effect of heavy-weight recycled materials on radiation shielding and properties of high-strength concrete with CEM III

This research aims to study the effect of replacing up to 100% of recycled coarse aggregates with heavyweight aggregates. In addition to the effect of adding heavyweight aggregate slag on the efficiency of shielding against radiation and on the mechanical physical properties and elevated temperature of heavyweight high-strength concrete (HWHSC). In this investigation, HWHSC mixtures incorporate lead slag (LS), copper slag (CS), and steel slag (SS) as coarse aggregate. Recycled heavyweight coarse aggregates are added to concrete mixtures at volume ratios of 0%, 25%, 50%, 75%, and 100%. Slump test, compressive strength, flexural strength, tensile strength, elastic modulus, and bulk density tests were carried out. Three different gamma-ray energies at 137Cs 662, 60Co 1173, and 60Co 1332 (keV) sources were used to evaluate the mass attenuation coefficient, linear attenuation coefficient, half and tenth-value layer, and mean free path. To evaluate the impact of elevated temperature on density, compressive strength, and radiation shielding properties, concrete mixtures were exposed to 22 °C, 300 °C, 500 °C, and 800 °C. Compared to basalt-based concrete, heavy-weight concrete (HWC) incorporating LS, CS, and SS coarse aggregate has a significantly higher density. The results show a good effect of recycled heavyweight coarse aggregates on fresh, mechanical, and radiation-shielding properties. The density of the developed high-strength concrete (HSC) mixes ranges between 2400 and 3370 kg/m3, and the increase in recycled heavyweight coarse aggregates replacement ratio up to 75% increased all mechanical characteristics of HWC mixtures. Using LS as a replacement of basalt by 75% resulted in the highest compressive strength, splitting tensile strength, flexural strength, and elastic modulus of 105.8 MPa, 14.2 MPa, 19.5 MPa, and 45.76 GPa, respectively. Compared to basalt, LS, CS, and SS eliminate the impact of elevated temperatures on HSHWC strength. The best radiation protection properties were achieved with the complete replacement of basalt by LS.

Investigation of radiation shielding properties of basalt-based glasses: Binodal/Spinodal decomposition effect theory

This study investigated the radiation protection properties of basalt glasses modified by adding Bi2O3 at different concentrations. The chemical composition of Basalt-Bi2O3 glasses is Basalt (100–x)–x Bi2O3, where x = 0, 10, 20, 30, 40, and 50 wt% represent G1, G2, G3, G4, G5, and G6 glasses, respectively. The radiation shielding parameters of the glasses were measured for gamma energies of 303 keV, 356 keV, and 662 keV using a high-resolution γ-ray spectrometer equipped with a high-purity germanium (HPGe) detector. Density values were calculated between 2.75 and 4.18 g/cm3 according to Bi2O3 contribution. Mass attenuation coefficients (MAC, cm2/g) were determined between 0.043 and 0.149 depending on the composition and applied energy. It has been determined that the Bi2O3 additive increases the radiation shielding properties of basalt-based glasses and is also effective in the shielding properties of the phase separation mechanism. Phase separation mechanisms caused inhomogeneity of electron densities, which affected the radiation shielding.

Gamma-rays shielding and antibacterial properties of coated fabrics

Today, with the development of technology, radiation exposure is more common. Therefore, alternative methods have been developed because shielding, which is used as the most effective method for radiation protection, has risks in terms of health. With the awareness of consumers, the use of antibacterial textile products has increased in terms of hygiene and comfort. In this study, for this purpose nano-silver which has antibacterial properties was applied to woven fabrics with the impregnation method and the fabrics were coated with tungsten and barium sulfate, which have radiation shielding properties. The radiation shielding properties of fabrics against 137 Cs source emitting γ radiation were investigated. In this study, woven fabrics with radiation protection and antibacterial properties, which are very important for the health sector, were obtained and compared with each other.

Investigation of the effect of cement type on nuclear shield performance of heavy concrete

This article studies the radiation shielding performance of three different concrete-added samples. First, the mass attenuation coefficient values of three distinct concrete materials were computed using the MATLAB code at energies ranging from 0.015 to 15 MeV, and the findings obtained were verified by theoretical WinXcom results. Half-Value Layer (HVL), Tenth-Value Layer (TVL), Mean Free Path (MFP), Effective Atomic Number (Zeff), Exposure Build-Up Factor (EBF), Energy Absorption Build-Up Factor (EABF) are the variables computed to assess available concrete samples in terms of radiation attenuation characteristics. The results demonstrated that the concrete sample with CAC possesses better gamma-radiation shielding characteristics. Concrete samples’ removal cross-sections (∑R) were obtained to analyze their ability to stop fast neutrons. Iron, aluminum, and lead-added concretes are better in terms of their density than the other types of concretes. Given the relationship between the density of the material and neutron shielding propensities, iron, aluminum, and lead-added materials are expected to better serve for shielding purposes. SRIM Monte Carlo code, as it is standard, was utilized to compute the mass stopping power (MSP) and projection range (PR) values. The concrete sample with CAC has shown better shielding properties compared to the others in the sample of the concretes having the lowest HVL, TVL, and MFP and highest ∑R. For proton and alpha particles, the concrete sample with CAC sample shows the best radiation shielding and protection properties. The concretes selected for the study are useful for shielding purposes compared to many other materials used in industry. In addition, radiation shielding concrete is cheaper than other shielding materials. It is easier to mold into different geometric shapes and is suitable for shielding from protons or alpha particles. Among the different concretes investigated in this study, it can be used for structures such as radiation oncology and nuclear medicine clinics in hospitals. Additionally, it can act as a biological shield for nuclear power plants, particle accelerators, and radionuclide laboratories, as well as other sources of radiation.

Investigation of the neutron radiation protective properties of chlorophyll and carotenoid

In this study, we have investigated neutron radiation absorption properties of chlorophyll and carotenoid. Our aim is to show that chlorophyll and carotenoid, which are naturally found in every green plant, can be used to make a cream, medicine, paint, or shield material against neutrons. Neutron radiation is generally used in many applications such as diffraction and scattering experiments, material crystallography, diagnosis and therapy in medicine, cell DNA studies in biology, condensed matter physics, materials research and development, solid-state chemistry, mineralogy, geology, and the study and improvement of the structural properties of materials. In order to reduce or completely eliminate the damages that can be caused by direct or scattered neutrons by the people working in these studies or other people in the environment, materials with high shielding are needed to absorb neutrons. In order to understand that chlorophyll and carotenoid can be used in the production of neutron shielding materials, the neutron radiation absorption parameters of these materials were investigated. The parameters, which are widely used in neutron shielding studies such as an effective removal cross section, half value layer, mean free path, and neutron transmission factor (NTF) were estimated using the Monte Carlo simulation GEANT4 code for both fast and epithermal neutrons. In addition, the dose rates of all samples were determined by using an 241Am–Be fast neutron source. All theoretical and experimental results obtained to understand the absorption capacities of chlorophyll and carotenoid were compared with paraffin, which is widely used in neutron shielding applications.It is to be noted that determined that chlorophyll showed an effective shielding against fast neutrons and carotenoid showed an effective shielding against epithermal neutrons. Investigation revealed that these materials are alternate shielding materials against neutron radiation for the production of medicine, composite material, and paint to be developed for neutron radiation.