Investigation of thermal, acoustic, mechanical, and radiation shielding performance of waste and natural fibers.

It is crucial to address two pressing global issues, energy shortage and environmental pollution, when producing building insulation materials. Using waste and natural fiber groups can be part of the solution. The insulation material was produced using pumpkin fiber, chicken fiber, cotton waste, vermiculite, and epoxy as binders.

A novel vanadium pentoxide doped glasses characterization for radiation shielding applications.

Glasses are actively used in various fields, from industry to health. Especially, special doped glasses used in radiation areas may vary depending on the type and energy of the radiation. Glasses made of high-density and effective radiation-absorbing materials generally provide adequate protection against X and gamma rays.

Preparation and study of radiation shielding features of ZnO nanoparticle reinforced borate glasses.

With the development of technology, the application areas of radiation have expanded and have an important place in our daily life. For this reason, we need more advanced and effective shielding materials to protect lives from the harmful effects of radiation. In this study, a simple combustion method was utilized to synthesize zinc oxide (ZnO) nanoparticles, and obtained nanoparticles' structural and morphological features were examined.

Simple parametrization of (n,d) cross sections using Flerov and Talyzin's formula.

This article aims at providing new cross section data from empirical formulas for the (n,d) reactions of which experimental measurements at 14-15 MeV energy are not available or limited. If the experimental data for a nuclear reaction at a given energy are scarce, theoretical calculations and also developing empirical formulas have a critical importance. Here, we propose a new empirical formula of (n,d) reactions for analysis of the relationship between the experimental data and the parameters of empirical formula.

(d, 3n) Reaction cross-section calculation of some reactor materials.

Nuclear reactions with charged particles have applications in many fields such as radioisotope production, industrial applications, astrophysics, etc. Therefore, examining the excitation functions performed and obtained by the activation technique is also important for understanding the nature of nuclear reactions. Also, it is especially necessary to study these reactions to estimate the effects of radiation damage on the fusion structural materials used in the construction of the first walls and core of the reactor.

Investigation of (d, 3n) reaction cross section using theoretical nuclear codes calculations on some nuclear materials.

It is important to examine the effects of the nuclear reaction, which is used as a building material in nuclear reactors. Nuclear reactions occur as a result of the interaction between incident particles with the target nuclei. The charged particle-induced reactions have prime importance in understanding the reaction mechanism which can be applicable to understand the particles resulting from the reaction.

Fabrication and characterization of GdxFeO(100-x) /PVA (x=0, 5, 10, 20) composite films for radiation shielding.

Purpose of this study is to investigate effect of gadolinium (Gd) content of GdxFe2O3(100-x), (x = 0, 5, 10, 20) composite system on structural, thermal, optical and radiation protection of poly (vinyl alchool) PVA based nanocomposite film. In this study, Gd doped FeO nanopowders (with Gd = 0, 5, 10 and 20) were synthesized by spray pyrolysis method. The characterization of these powders have been obtained by using X-ray diffractometer (XRD), scanning electron microscopy (SEM), and Uv-vis spectrometer.

Investigation of (γ, p) reaction cross-section calculations of Ca, Ge and Zr isotopes.

Calcium, Germanium and Zirconium isotopes can be used in semiconductors, fuel rods and as cooling materials in nuclear reactor technology. During the various occurred reactions in reactors, gas production via gamma reactions or temperature rise can severely damage the reactor materials. Therefore, it is necessary to know the effects of particles interacting with nuclear reactor materials in such cases.

The empirical cross section behavior of (d, 3n) reaction for 20±1.5 MeV energy.

Many nuclear reaction cross-section formalism has been developed for particle induced reaction up to date. In this study, a new empirical (d, 3n) cross section formulae systematic have been developed at 45≤A≤112 mass range for 20 ± 1.5 MeV incident deuterium energy.

A new formulae study for the (n,2p) reaction cross-section systematics at 14-15 MeV.

The cross-section calculation systematics for nuclear reactions have great importance in describing the particle-induced excitation of nuclei. In this study, for 14-15 MeV of incident neutron energy, it has been suggested new empirical formulae to describe the (n, 2p) reactions cross sections. The new empirical formulae have been obtained for 29≤A≤159, 29≤A≤103 and 133≤A≤159 mass ranges which are dependent on s=(N-Z)/A asymmetry parameter.