Investigation of radiation attenuation properties for baryte concrete

In the present work the authors have studied the attenuation properties of baryte concrete as a biological shield for nuclear power plants, particle accelerators, research reactors, laboratory hot cells and different radiation sources. Investigation has been performed by measuring the transmitted fast neutron and gamma ray spectra through cylindrical samples of baryte concrete (p = 3.49 g(.)cm(-3)). A reactor-collimated beam and neutron-gamma spectrometer with stilbene scintillator were used during measurements. A pulse shape discriminating technique based on zero cross over method was used to discriminate between neutron and gamma pulses. Removal cross-section Sigma(R.eff) and total attenuation coefficient mu(eff) of neutrons and gamma rays were evaluated from the obtained results. Also, slow neutron fluxes have been measured using a collimated reactor beam and BF3 counter, where the macroscopic cross section Sigma(E-n) has been evaluated using the attenuation relation. The total macroscopic cross sections Sigma(T)(E-n) and total attenuation coefficient mu(E-g) of neutrons and gamma rays have been calculated based on the database cross sections. Also, the total mass attenuation coefficient mu(eff)(Eg)/p and mu(E-g)/p of gamma ray have been estimated and calculated using the measured results and XCOM code respectively. Measured and calculated results were compared and a reasonable agreement was found.