**4. Conclussions**

320 Nuclear Reactors

**Code of Sample Attenuation Length (cm)**  4F0 31.92848 4F15 25.25253 6F0 23.96932 6F15 22.47191 8F0 46.04052 8F15 15.15611 4S0 20.96876 4S15 17.55618 6S0 27.31494 6S15 19.46283 8S0 73.20644 8S15 54.79452

**Code of Sample µ(cm-1)** 

4F0 0.0313 4F15 0.0396 6F0 0.0417 6F15 0.0445 8F0 0.0217 8F15 0.0650 4S0 0.0477 4S15 0.0570 6S0 0.0366 6S15 0.0514 8S0 0.0137 8S15 0.0183

As can be seen from Fig.5 and Table.4, dose transmission values and attenuation lengths decrease with increasing fiber steel and silica fume contents. This result indicates that neutron shielding capacity of samples is increased by silica and steel amount. According to the results, there is not a consistent relationship between vermiculite content and neutron shielding capacity of samples except of F15-samples. The sample named 8F15 is the best neutron attenuator in all specimens. The reason of this that, this sample has higher vermiculite and fiber steel content than others. The worst sample is 8S0 which has higher vermiculite but lower silica fume content. As a result, to increase neutron shielding capacity

of sample, expanded vermiculite and fiber steel may be added in the mortar.

Table 4. 4.5 MeV neutrons attenuation lengths

Table 5. 4.5 MeV neutron total macroscopic cross sections

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

