Attenuation properties and gamma heating of three local types of a radiation shielding concrete

The computer code SABIN-3 based on the removal-diffusion techniques is used to investigate the attenuation properties and gamma heating rates of three types of a radiation shielding concrete made of Iocal materials in Libya. Calculations were performed using a typical WER reactor core as a radiation source. The three types of concrete are an ordinary concrete, Serpentine concrete and magnetite-limonite concrete with densities of 2.3 ,2.3 and 2.6 g/c m3 respectively, a thickness of 68 cm in radial direction of the core is considered for each type. The neutron fluxes distribution and gamma heat rates are calculated using the computer code SABINE-3. The attenuation behavior of neutrons and gamma rays in the concrete shields under investigation were analyzed. The obtained results of neutron relaxation length and the attenuation properties are compared with the corresponding values given by others for the same types of concrete. This comparison showed a good agreement and indicated that these three types of concrete possess all requirements for concrete shields that can be used for constructing the biological shields around nuclear reactors and other nuclear installations. Activity Ra is 436.1±199 Bqkg-1 calculated in marble. The highest radioactivity level and dose rate in air from these materials were calculated in marble