Gamma-ray Attenuation Coefficients Research Articles

Investigation of impact of soil texture, depth and gamma ray energy on the mass attenuation coefficient and determination of soil bulk density using Gamma-Ray Spectrometry

The determination of the gamma-ray attenuation coefficient is a critical parameter in the characterization of the extent and diffusion of gamma radiation within intricate materials, such as soil. Soils exhibit a complex and diverse composition, characterized by the presence of several phases, including minerals, gasses, organic matter, water, and metals. The study demonstrates the utilization of gamma-ray spectrometry to determine the mass attenuation coefficient and soil bulk density. The impact of incident gamma-ray energy, soil texture, and soil depth on the mass attenuation coefficient is also investigated. The experimental measurements were conducted utilizing a gamma spectrometer equipped with a 2″ × 2″ NaI(Tl) detector at gamma energies of 0.356, 0.662, and 1.332 MeV using 133Ba, 137Cs, and 60Co sources, respectively. The soil samples corresponding to two textures and three depths were collected from the research farms of the Department of Soil Science, Punjab Agricultural University, Ludhiana. The study revealed that the attenuation coefficient depends on the energy of incident radiation and the nature as well as the composition of the soil. The mass attenuation coefficient was observed to decrease rapidly with the increase in gamma radiation energy. Mass attenuation coefficient was found to be higher for sandy loam compared to sandy clay loam textured soil. Moreover, the attenuation coefficient was higher for the lower depths than the upper depth. The comparison between the experimental and predicted values of the mass attenuation coefficient, utilizing the XCOM-NIST framework, demonstrated a satisfactory level of concordance within a 10% margin for gamma energies measuring 0.356 and 0.662 MeV. However, the agreement was slightly less favorable, with discrepancies of less than 12% for sandy clay loam samples and less than 15% for sandy loam textured soil samples, when examining a higher gamma energy of 1.332 MeV. The measured value of mass attenuation coefficient was used to calculate soil bulk density, which agreed reasonably well with the values obtained with the conventional method. Specifically, the sandy clay loam samples displayed a range of 7–14% deviation, while the sandy loam textured soil samples exhibited a range of 14–23% deviation. The investigation can be expanded to ascertain significant soil properties, such as porosity and moisture content.

Study of the structural and shielding properties of unsaturated polyester/lead oxide nanocomposites against gamma-rays

In this study, lead oxide nanorods were synthesized without surfactants in an aqueous medium at room temperature. Different percentages of lead oxide nanorods were added to an unsaturated polyester polymer matrix to have various wt% nanocomposites. The gamma-ray mass attenuation coefficients were measured as a function of the weight percentages of lead oxide at different thicknesses. This was done with radioactive source Ra-226. The unsaturated polyester/lead oxide nanorods composite was treated with 1, 2.5, 5, 10, 15, 20, 40, and 60 wt% lead oxide nanorods, as different proportions of the filler. According to the results, the best radiation attenuation was for 60 wt% nanocomposite. In such a nanocomposite, the optimal half value layer, tenth value layer, and mean free path were about 2.4, 7.6, and 3.35 cm, respectively.

An Experimental Study on the Measurement of Gamma-Ray Linear Attenuation Coefficients with Transmission Factors for Ispir and Kızılcahamam Dry Bean

In the present work, the gamma-ray linear attenuation coefficients (µ) and transmission factors (TF) were measured for Erzurum Ispir dry bean (IDB) and Ankara Kızılcahamam dry bean (KDB). Photons of the Am-241 point source with an energy of 59.54 keV, an Energy Dispersive X-Ray Fluorescence Spectrometer (EDXRFS), and a Si (Li) detector were used in the experiment. As a result, it was observed that the average transmission factor of Erzurum İspir dried beans was higher than that of Ankara Kızılcahamam dry beans, and the average linear attenuation coefficient was smaller. This means that Ankara Kızılcahamam dry beans absorb more gamma rays than Erzurum İspir dry beans, that is, they interact more with gamma rays.

Mechanical, Durability, and Gamma Ray Shielding Characteristics of Heavyweight Concrete Containing Serpentine Aggregates and Lead Waste Slag

Heavyweight concrete is used to prevent harmful radiation for the construction of hospital, military, and nuclear power plants and also to increase the durability for the construction of marine concrete structures. In this research, using a combination of serpentine aggregates and lead slag, the mechanical, durability, impact resistance, and shielding properties of heavyweight concrete were examined. The variables included fine and coarse serpentine aggregates, which were replaced with normal fine and coarse aggregates in amounts of 0, 25, 50, and 100 percent, respectively. The lead slag in all samples was considered constant. Slump, compressive strength, flexural strength, water penetration depth, impact resistance (drop hammer), and gamma ray attenuation coefficient tests were conducted. The chemical composition of serpentine aggregates and lead slag were evaluated by X-ray powder diffraction. The results showed that the density and linear attenuation coefficient (LAC) increased with the increase of fine and coarse serpentine aggregates in heavyweight concrete containing lead slag. The highest density and LAC were obtained in a sample in which 100% fine serpentine aggregates and 100% coarse serpentine aggregates were used. Using 25% of serpentine fine aggregates and 25% of serpentine coarse aggregates in heavyweight concrete samples containing lead slag has achieved the highest compressive strength and flexural strength. But with the increase of fine and coarse serpentine aggregates to more than 25%, the upward trend of increasing compressive strength decreased. Silica constitutes a large part of the chemical structure of serpentine aggregates (about 42%). Increasing the amount of serpentine aggregates in concrete mixes leads to excessive release of calcium hydroxide in concrete. This issue can lead to the formation of a weak zone in concrete and decrease the compressive and impact resistance.

Low-cost piezoelectric sensors and gamma ray attenuation fabricated from novel polymeric nanocomposites

<abstract> <p>This study looks at the synthesis of innovative PEO/PVA/SrTiO<sub>3</sub>/NiO nanocomposites for piezoelectric sensors and gamma shielding applications that are low weight, elastic, affordable and have good gamma ray attenuation coefficients. The impact of SrTiO<sub>3</sub>/NiO on the structural characteristics of the PEO/PVA mixture is investigated. The polymer mixture PEO/PVA received additions of SrTiO<sub>3</sub>/NiO at concentrations of (0, 1, 2, 3 and 4) weight percent by the casting method. On the top surface of the films PEO/PVA/SrTiO<sub>3</sub>/NiO NCs, scanning electron microscopy reveals several randomly distributed aggregates or fragments that are consistent and coherent. An optical microscope image collection reveals that the blend*s additive distribution of NPs was homogenous. Gamma ray shielding application results show that the attenuation coefficient of PVA/PEO/SrTiO<sub>3</sub>/NiO NCs is increased by increasing concentration of SrTiO<sub>3</sub>/NiO nanoparticles. Radiation protection is another application for it. The pressure sensor application findings of NCs show that, when the applied pressure rises, electrical capacitance (Cp) increase.</p> </abstract>

Radiation shielding capacity of Li2O-SiO2/GeO2 glasses doped with rare earth oxides: Nuclear security applications

In the present work, the ionizing radiation (namely, gamma-rays, charged particles, and neutrons) attenuation parameters of Li2O–SiO2 (denoted as LS) and Li2O–SiO2–GeO2 glasses doped with Y2O3 and In2O3 (LGY and LGI) glasses were estimated and analyzed with the aim of exploring their shielding potentials. The gamma-ray transmission attenuation coefficient was simulated by the FLUKA code and also estimated by XCOM. Also, the stopping powers and ranges of electrons, protons, α-particles, and carbon ions were estimated for particle kinetic energies within 15–15000 keV. The fast and thermal (25 meV) neutron cross-sections were estimated for the three glasses. At 15 MeV, the mass attenuation coefficient is 0.019, 0.021 and 0.022 cm2/g while the linear attenuation coefficient magnitude varied within the range of 0.047–11.564 cm−1, 0.061–32.008 cm−1 and 0.068–38.122 cm−1 for LS, LGY, and LGI, respectively. The effective atomic number varied from 8.21 to 12.00 for LS, 8.71–22.71 for LGY, and 8.78–26.37 for LGI. Likewise, the charged particle shielding ability of the glasses was in the order: LS < LGY < LGI. This trend was conserved for the neutrons’ cross-sections. Compared to conventional and recently researched shields, LS, LGY, and LGI present viable alternative glass shields in nuclear radiation applications.

Synthesis, microstructure, and formation mechanism of a potential neutron shielding material: WAlB

• Dense, predominately single-phase samples of WAlB were synthesized using a reactive hot press sintering method for the first time. • DFT calculations and Rietveld analysis of WAlB indicate that WAlB most likely forms via a topotatic transformation reaction, by the intercalation of Al layers into WB crystal structure. • The calculated linear attenuation coefficients for different energy gamma-rays imply WAlB has a high gamma-ray shielding capacity.

Effect of nano ferrosilicon and heavyweight fine aggregates on the properties and radiation shielding of ultra-high performance heavyweight concrete

Minerals such as ilmenite and magnetite better absorb gamma rays compared with silica aggregates because of their elevated densities. However, utilizing such minerals as key elements in ultra-high performance heavyweight concrete (UHPHWC) demonstrates promising outcomes, in addition to the enhanced tensile strength of the optimum radiation absorber for nuclear sites. This paper presented ilmenite and magnetite separated from black sand for use as substitutes for fine aggregates in the production of UHPHWC. In addition, nano ferrosilicon (NFS) at 1%, 2%, and 3% of the cement mass was developed using a mechanical method and mixed into the UHPHWC mixes. Their effects on the microstructure, gamma-ray attenuation coefficient, mechanical properties, and density of UHPHWC were explored. The total replacement of fine sand with ilmenite and magnetite enhanced the attenuation efficiency of the concrete mixes by 18.9% and 24.2%, respectively, after 28 days. The addition of 3% NFS to produce UHPHWC achieved the highest compressive strengths of 130.5, 167.2, and 189.8 MPa after 7, 28, and 91 days, respectively. In addition, the combination comprising 3% NFS and 100% magnetite acquired the maximum density and gamma-ray attenuation coefficient values.

Enhancement on radiation shielding performance of B2O3 + Li2O + ZnO + Na2O glass system

Three borate glasses with the chemical composition 50B2O3 + xLi2O + 20ZnO + (30 - x) Na2O (where x = 5, 10, & 20 mol. %) and coded as BLZN-A, BLZN-B, and BLZN-C were reported and investigated for their gamma-ray, charged particle (electrons, protons, alpha particles and carbon ions), and neutrons shielding viability. The gamma ray attenuation coefficients were computed by the FLUKA simulations and XCOM methods, while the stopping powers and range of the particles were evaluated based on SRIM software and NIST database. The obtained results showed that gamma-ray and charged particle shielding ability increases for the present glass samples in the order of BLZN-A < BLZN-B < BLZN-C for radiation energies of 0.01–10 MeV. The removal cross section corresponds to 0.106, 0.1087, and 0.1132 cm−1 for BLZN-A, BLZN-B, and BLZN-C, while the total cross section for thermal neutron is 69.91, 71.46, and 73.83 cm−1. The shielding performance of the glasses is higher than those of some conventional shields such as ordinary concrete and commercial glass shields. Thus, the present BLZN glass system have huge potential for practical applications in hospitals and nuclear facilities.

Valorization of nano-PbO as an additive to modify the properties and radiation shielding of alkali-activated slag mortar

In this work, for the first time, the possibility of employing nano-lead oxide (nPbO) in alkali-activated slag (AAS) mortar as a modifier agent for its properties was studied. Different ratios of nPbO (0 wt%, 1 wt%, 3 wt% and 5 wt%) were added to the plain AAS mortar. The effects of these ratios on flowability, mechanical strength, water absorption, total porosity, aging resistance, gamma-ray radiation shielding, crystalline phases, thermal analysis and microstructure were investigated. The gamma-ray attenuation coefficients were determined as a function of the additive percentages of lead oxide for gamma-ray energies of 1332, 1173 and 662 keV using Co-60 and Cs-137 sources. Different techniques were used to analyze the results. The results showed higher flowability of the mixtures with introducing nPbO. The flowability increased with increasing nPbO ratio. The mechanical strength and aging resistance increased with introducing 1% and 3% nPbO, then slightly decreased with including 5% nPbO. Water absorption and total porosity decreased with introducing 1% and 3% nPbO, then slightly increased with including 5% nPbO. Introducing nPbO in the AAS system improved the radiation properties, of which the attenuation coefficients increased with including nPbO. In a word, using suitable ratios of nPbO improved the fresh, hardened, durability and radiation properties of AAS mortar and can provide it for wider applications.

Effect of Fe2O3/Al addition on the neutron shielding, microstructure, thermal, and mechanical properties of HDPE composites

High-density polyethylene (HDPE) has been reinforced with various ratios of iron oxide (α-Fe2O3) and aluminum (Al) nanoparticles (NPs) to be used as shielding materials against nuclear radiation. The examination of scanning electron microscopy images (SEM) reveals small polymeric agglomerations besides the uniform dispersion of Al and α-Fe2O3 NPs. Also, all stress parameters () decremented after incorporating the 40 wt% α-Fe2O3 NPs into the HDPE matrix. Meanwhile, the mutual additions of Al powder with α-Fe2O3 NPs in samples P2 (30% α-Fe2O3/10% Al) and P3 (20% α-Fe2O3/20% Al) led to improving the tensile parameters. These results may be due to the physical reactions between α-Fe2O3 NPs and Al powder and polymeric chains. Generally, the polymeric materials are characterized as low-cost and lightweight compared to standard shielding materials. The fast neutrons and gamma-rays shielding properties of the prepared samples were experimentally measured using a shielded 239Pu-Be source and stilbene detector. The neutron removal cross-section () and gamma-ray liner attenuation coefficient (μ), in addition to the mean free path (MFP) and the half-value layer (HVL) for the prepared samples, have been calculated. The results showed that the nanocomposite containing 40% iron oxide had improved the neutron and gamma-ray shielding properties compared to the pure HDPE and other prepared nanocomposites. The values of MFP and HVL indicate that the prepared nanocomposites can be used for shielding gamma-rays and neutrons from radioactive isotopes and from other nuclear radiation facilities compared to common shielding materials such as concrete.

Silicone rubber composite reinforced by bismuth tungsten oxide as an effective gamma ray protective materials

The workers’ continual exposure to nuclear radiation makes it indispensable to invent and form lightweight materials as flexible radiation shields. So, in this article, silicone rubber SR inlaid with varying filler ratios of bismuth tungsten oxide Bi2(WO4)3 was produced. Mechanical properties, hardness, tensile strength, tensile modulus, and elongation at break, of the SR/Bi2(WO4)3 composites were studied as a function of filler concentration and irradiation dose. The Bi2(WO4)3 filler enhanced these properties. On the other hand, with augmentation of irradiation dose, hardness of the SR/Bi2(WO4)3 composites increased and the other mechanical properties decreased. Under accurate geometry conditions, the gamma ray attenuation coefficients of the SR/Bi2(WO4)3 composites were studied at the energies 661.66, 1173.24, and 1332.5 keV. The attenuation parameters, linear attenuation coefficients mu, experimental mass attenuation coefficients {sigma }_{exp.}, and half value layer HVL results revealed that the attenuation ability of the composite was enhanced with the increase of Bi2(WO4)3 concentration. The results of {sigma }_{exp.} were confirmed through their congruence with the theoretical calculations of mass attenuation coefficients {sigma }_{theo.} Considering the merits of lightweight, high mechanical properties, superior attenuation ability, and appropriate irradiation resistance, the produced SR/Bi2(WO4)3 composite is suitable as durable and flexible gamma ray shields such as anti-radiation coats, gloves, shoes.

Cerium (IV) oxide reinforced Lithium-Borotellurite glasses: A characterization study through physical, optical, structural and radiation shielding properties

The purpose of this study was to characterize the structural, optical, and physical properties of various kinds of glasses based on the 50TeO 2 –30B 2 O 3 -(20-x)Li 2 O-xCeO 2 system (x = 0, 0.5, 1, 2, 3, 4, 5, 10, 15, 20). Consequently, ten glass samples were produced by melting-annealing. Calculations of the densities of the synthesized glasses were performed using the Archimedes technique. The sample's structural, optical, physical, and radiation interaction properties were determined using XRD analysis, Raman spectroscopy, and advanced modelling techniques with FLUKA code, yielding optical band gap, refractive index, and Urbach energy values. By increasing the CeO 2 reinforcement from 0 to 20 mol %, the glass densities rose from 4.0614 to 4.7519 g cm −3 . The transmittance spectra of TBLC glasses were found in the range of 200–1100 nm. Our findings showed that the lowest Urbach energy belonged to the TBLC1 sample, and the highest Urbach energy belonged to the TBLC20 sample. When the CeO 2 ratio was raised, the optical transmittance and absorption characteristics changed nearly monotonically, suggesting that these qualities may be calculated and controlled using the CeO 2 additive, as shown in this experiment. By substituting CeO 2 for Li 2 O inside the structure, it was possible to substantially enhance the optical band gap. Additionally, at simulated energies greater than 0.02 MeV, the gamma-ray linear attenuation coefficient rises monotonically with CeO 2 reinforcement. Consequently, linear attenuation coefficients were reported as 125.843 cm −1 , 127.601 cm −1 , 129.211 cm −1 , 132.312 cm −1 , 135.166 cm −1 , 138.705 cm −1 , 141.288 cm −1 , 156.690 cm −1 , 172.393 cm −1 , 186.811 cm −1 for TBLC0, TBLC0.5, TBLC1, TBLC2, TBLC3, TBLC4, TBLC5, TBL10, TBLC15 and TBLC20 at 0.015 MeV, respectively. It can be concluded that combination of high-concentration CeO 2 and TeO 2 –B 2 O 3 glass is an excellent synergetic tool for combining structural, optical, and radiation properties when combined with other materials.

Assessment of Radiation Shielding Properties of Polymer-Lead (II) Oxide Composites

Long term exposure to very high levels of radiations from medical diagnostic centres, industries, nuclear research establishments and nuclear weapon development have resulted in health effects such as cancer and acute radiation syndrome, hence the need for proper radiation shielding. This paper investigated Epoxy-Lead (II) Oxide (PbO) composite as radiation shielding. The composites were prepared by dispersion of microsized PbO particles into polymeric materials using effective melt-mixing method and cast in a 4 cm by 6 cm rectangular aluminium Mold with a thickness of 5 mm and was allowed to set over night at room temperature. The gamma ray attenuation ability of the composites were studied using gamma ray transmission or attenuation coefficient determination for the gamma ray energy. Three gamma ray sources Ba-133, Cs-137 and Co-60 were employed. The density, linear attenuation coefficient, half value layer (HVL), relaxation length and heaviness of the samples were determined. The measured values of linear attenuation coefficient increased with increasing filler concentration in all the samples at all gamma ray energies. It was also noticed that 40 % and 50 % filler samples attenuates more relative to the other samples under study. The maximum linear attenuation attained was found at energy of 662 keV. The composites have been found to possessed medical gamma-ray attenuation characteristics among the sample materials over a certain photon energy range (0.08 MeV–1.332 MeV) and found useful as a biological radiation shielding against gamma rays.

Experimental Investigation of gamma-ray shielding capability of clay used as building materials in Thi Qar Province

Clay is one of the oldest building materials known to man uses in construction. This material has many important potentials and features, and the methods of using this material in construction in the past and present varied greatly, responding to environmental determinants; Such as the climate, the quality of the soil, and the available materials on the one hand. The aim of the present study is to test the ability of this material to attenuate gamma-ray radiation. Gamma ray attenuation coefficients such as linear and mass attenuation half value layer, tenth value layer, and mean free path for deferent thickness slabs of clay was measured using 3”×3” NaI(Tl) gamma spectroscopy system at energy 662 KeV, 1173 KeV, and 1332 KeV. The measured values of the attenuation parameters showed good agreement with the theoretical calculations. The elemental compositions of the clay slabs analyzed by using an EDXRF spectrometer. The obtained results appear that the clay is a suitable alternative for radiation protection and achieve a safe level of radiation exposure for photons that have moderate energy.

Fabrication, structural, optical, physical and radiation shielding characterization of indium (III) oxide reinforced 85TeO2-(15–x)ZnO-xIn2O3 glass system

This work aimed to evaluate the structural, optical, and physical features of several types of glasses based on 85TeO2-(15–x)ZnO-xIn2O3 (x = 2, 4, 6, and 8 mol%) system. As a result, five different samples were synthesized utilizing the melting-annealing technique. The Archimedes method was used to calculate the densities of the synthesized glasses. The structural, optical, physical, and radiation interaction characteristics of the sample were determined using XRD investigations, Raman spectra, and advanced modelling methods, producing optical band gap, refractive index, and Urbach energy values. The glass densities increased from 5.6091 g cm−3 to 5.6754 g cm−3 by increasing In2O3 reinforcement from 2 to 8 mol %. Urbach energies increased consistently from 0.1399 to 0.1439 eV as In2O3 concentration increased, apart from a drop to 0.1345 eV at x = 8. The optical transmittance and absorption characteristics altered nearly monotonically with increasing In2O3 ratios, showing that these characteristics may be estimated and controlled using In2O3 additive. By substituting ZnO with In2O3 within the structure, the optical band gap was dramatically enlarged. Additionally, at simulated energies greater than 0.02 MeV, the gamma-ray mass attenuation coefficient grows monotonically with In2O3 reinforcement. As a result, it can be stated that the high concentration In2O3 to TeO2–ZnO glass combination is a good synergetic tool for integrating structural, optical, and radiation properties.

Neutron and gamma radiation shielding Ni based new type super alloys development and production by Monte Carlo Simulation technique

In the present study, five different type of new super alloys have been developed and produced which have high temperature resistance for both gamma and fast neutron radiation shielding. These super alloys have been produced with powder methodology by using the materials such as iron (Fe), rhenium (Re), boron carbide (B4C), nickel (Ni), chromium (Cr), boron (B), copper (Cu), tungsten (W), tantalum (Ta). Gamma-ray Mass attenuation coefficients, half value layer effective atom number, mean free path and fast neutron total macroscopic cross section, transmission number values have been theoretically calculated by using Geant 4 code, WinXCom and Phy-X / PSD software. In addition, experimentally equivalent dose measurements have been carried out by using 241Am-Be fast neutron source. Sulfuric acid abrasion, compressive strength, temperature resistance and weldability tests have been made. The results are compared with 316LN nuclear stainless steel because of its common use in nuclear shielding applications and all new type super alloy samples have shown better radiation absorption ability for both gamma and fast neutron. It has been determined that these new type super alloys can be used in nuclear applications for better shielding.

Influence of PbO content on the gamma ray shielding properties of lead boro-telluro-phosphate glasses

This paper investigates the influence of lead monoxide (PbO) content on the gamma ray attenuation coefficients of boro-telluro-phosphate glasses. The MCNP5 simulation code has been applied to estimate the mass attenuation coefficients (μ/ρ) of Sm3+ doped (60-x)B2O3-xPbO-14TeO2-10P2O5-7.5BaO-7.5CdO-1Sm2O3 (x = 0, 10, 20, 30 and 40 wt%) glass system within 0.02–10 MeV photon energy range. The MCNP5 simulated results are accord with the theoretical XCOM results perfectly. The results show that the increasing content of PbO in the glass compositions can improve the gamma ray shielding capability of the studied glasses. With the biggest content of PbO in Pb40B20 glass, superior HVL and Zeff values are observed. The values of HVL for Pb40B20 glass vary from 0.0035 to 3.6824 cm, and the values of Zeff vary from 25.94 to 70.05 depending on the photon energy 0.02–10 MeV. In addition, the boro-telluro-phosphate glasses have been compared with types of commercial concretes and glasses in terms of HVL.

A Different Method to Determine the Gamma-ray Linear Attenuation Coefficient

Gamma-ray linear attenuation coefficient values of Pb, Fe, and Al absorber materials were investigated. A fast coincidence timing measurement spectrometer was used for this purpose differently from other traditional spectrometers. A solid point 22Na positron source was utilized for the annihilation radiations. Obtained results were compared with those of XCOM program and literature values.

Investigation of gamma-ray attenuation coefficients for solid boronized 304L stainless steel

In this study, mass attenuation coefficient (μ/ρ) and half value layer (HVL) at Eu-152 and Co-60 energies were used in measuring attenuation coefficients of the solid boronized AISI 304L stainless steel at 950 °C for 2, 4, 6 and 8 h. The experimental mass attenuation coefficients, μ/ρ, and HVL for these materials were compared to theoretical values obtained with WinXCOM. At the same time a new boriding agent (Baybora®-1) also developed for solid boriding method was used. The effects of boron layer size on radiation attenuation of boronized composites were evaluated in relation with gamma-ray transmission and the results of the experiments were interpreted. It could be understood that increased of boron layer in AISI 304L causes of increases in the attenuation coefficient values. The measured values agree with the theoretical values. The interaction parameters for selected samples have been computed and provided in the extended energy range 10−3–104 MeV. The shielding properties prepared stainless steel have also been compared with standard concretes as well as with the standard shielding stainless steel. It is found that the prepared stainless steel is the better shielding substitute to the conventional concretes as well as other standard shielding stainless steel. So, submicron size boron layer used composite materials are more convenient than micron size boron used composite materials as radiation shielding materials for nuclear applications.