Nowadays concrete is often used in radiation shielding process. In several studies, some additive materials were added in concrete to increase its radiation shielding capacity. In this study, as an additive material, we have used vermiculite mineral with a good heat insulation material. Produced samples have three different vermiculite and cement ratio values. 4.5 MeV neutron dose transmission values (Fig.5) and attenuation lengths of samples (Table.4) were obtained. Attenuation length is just equal to the average distance a particle travels before being scattered or absorbed. It is a useful parameter for shielding calculations. Also we calculated experimental 4.5 MeV neutron total macroscopic cross sections (p) using by dose transmission values. The various types of interactions of neutrons with matter are combined into a total cross-section value:

у — у + у + у

total scatter capture fission

The attenuation relation in the case of neutrons is thus:

(2)

(3)

where I0 is known as beam intensity value, at a material thickness of x = 0. Equivalent dose rate has been used instead of beam intensity because of our equivalent dose rate measurements. Experimental 4.5 MeV neutron total macroscopic cross sections were shown in Table.5.

2. Conclussions

At the end of this experimental study, we reached the following outcomes;

1. Vermiculite mineral has high-level thermal insulation capacity. Concrete isn’t decomposing with vermiculite addition. This mineral can be used as an additive for radiation shielding process.

2. According to the experimental results, neutron shielding property of concrete increase with increasing fiber steel and silica fume content.

3. To produce good materials which have high radiation shielding capacity and thermal insulation property, vermiculite and fiber steel may be doped in mortar. These materials can be used for neutronic and thermal applications.