Monte Carlo simulation on shielding properties of neutron-gamma from 252Cf source for Alumino-Boro-Silicate glasses

Simulation and prediction of the attenuation behaviour of the KNN-LMN-based lead-free ceramics by FLUKA code and artificial neural network (ANN)-based algorithm

The significance and novelty of the present work are the preparation of the non-lead ceramic by the general formula of (1-x) K_0.5Na₀.₅NbO₃-xLa Mn_0.5Ni_0.5O₃ (KNN-LMN) with different x (0<x<0.295) (mol) to examine the shielding qualities of KNN-LMN non-lead ceramic via FLUKA code. The obtained results via FLUKA code are used as input data for training the artificial neural network algorithm and prediction. For this purpose, the radio isotopic ²⁵²Cf neutron source is simulated by the HI-PROBE, RADDECAY and DCYSCORE cards using the FLUKA code. As a result, the neutron-gamma photon shielding ability of the KNN-LMN lead-free ceramics exposed to the ²⁵²Cf neutron source is estimated and predicted. Findings show that by increasing the concentration of the x in (1-x) K_0.5Na₀.₅NbO₃-xLa Mn_0.5Ni_0.5O₃ lead-free ceramics results in an ascending trend in density. In addition, the increment of the x rate (x refers to the concentration of La Mn_0.5Ni_0.5O₃ in KNN-LMN non-lead ceramics) causes an increase in the value of the neutron attenuation parameter (∑t), and a strong relationship is monitored between ∑t and density. Moreover, descending order of (HVL)x=0.01>(HVL)x=0.04>(HVL)x=0.07>…>(HVL)x=0.25 is reported for half-value layer values against gamma photon. From the attained results, it can be concluded that increaisng the rate of x results in the better shielding proficiency in terms of neutron and gamma photon for chosen KNN-LMN-based lead-free ceramics.

An extensive study on the neutron-gamma shielding and mass stopping power of (70-x) CRT-30K2O-xBaO glass system for 252Cf neutron source

The present study focuses on the charged-uncharged particles shielding performance of the addition of a mixed type of cathode ray tube (CRT) in a glass system that is irradiated by the ²⁵²Cf neutron source via the MCNPX simulation and analytical calculations, as well as Phy-X: PSD and SRIM software. The CRT waste glass is inserted into the glass system with (70-x) CRT-30K₂O-xBaO general formula for x = 0, 10, 20 mol% that produces CG1, CG2, and CG3 glass shielding materials. Using Watt Fission Distribution (WFD) and Doppler Effect (DE) the neutron-gamma photon spectra were extracted for shielded (in the presence of the glass materials) and unshielded (in air) cases. Some calculated attenuation parameters related to the neutron deduced that CG1 is the best neutron attenuator among the selected glass samples. Moreover, by increasing the density of the glass from CG1 to CG3, the ascending trend is observed for the linear attenuation coefficient (LAC, cm^-1) of the studied glass, and the best shielding competence is monitored for CG3. Furthermore, two sharp peaks are found in Z_eff graphs which may be due to K-edge absorption of Ba and Pb elements and by decreasing the Pb element from CG1 to CG3 the second peak gradually becomes smooth. In addition, Mass Stopping Power/ Projected Ranges of the proton (H¹) and alpha particles (He⁺²) are also estimated by SRIM code and findings show that CG1 can better stop proton and alpha particles in comparison with the other chosen glass structures.

Variation in gamma ray shielding properties of glasses with increasing boron oxide content

The study of radiation shielding properties for a material is an important part of research in scientific world. It is expressed in terms of the linear linear coefficients (LAC) which can also be used to obtain some other parameters. The gamma shielding properties of glass with addition of boron oxides in different amounts were studied, thereby obtaining linear attenuation coefficients (LAC), mean free path (mfp), Exposure Buildup factor (EBF) which were calculated using Phy-X/PSD code. It was found that increasing boron oxide content of 0, 2, 4, 6, 8 (w %) in glass increased the gamma attenuation coefficients.

Bi2O3–PbO–CdO–B2O3 glasses: competent candidates for radiation shielding

The Bi2O3–PbO–CdO–B2O3 glasses were shaped via the melt-quenching process. The XRD spectra reveal that the glasses are composed of amorphous material. Four distinct bands may be seen in the FTIR spectra at wavelengths between 400 and 600, 600–800, 800–1200, and 1200–1500 cm−1 range. This is due to a variety of bond stretching and vibration modes present in the system. A Monte Carlo simulation was used to verify the radiation shielding capabilities. The µ values grow as the amount of Bi2O3 in the manufactured glasses increases. The rise in µ values was coupled with a drop in the Δ0.5 values when the Bi2O3 concentration was increased. Additionally, the TF and RPE values were influenced by the enhancement in the µ values, with the RPE increasing from 34.61 to 44.42 percent and the TF values decreasing from 65.39 to 55.58 percent at 0.662 MeV when the Bi2O3 concentration was increased. The study showed that raising the Bi2O3 content improves the shielding capabilities. Thus, the produced glass samples, particularly BPCB25, exhibit excellent shielding capabilities, making them suitable for use in radiation shielding fields.