Author/Authors :
Makarious، نويسنده , , A. S.; Bashter، نويسنده , , I. I.; Abdo، نويسنده , , A. El-Sayed; Azim، نويسنده , , M. Samir Abdel; Kansouh، نويسنده , , W. A، نويسنده ,
Abstract :
This work IS concerned with the use of ilmenite concrete (density = 3.5 glcml) prepared from
local materials as a radiation shield. Comparison with a previously investigated ilmenite concrete (density =
4.6 glcm 1) including iron punching additions in its constituents have been carried out as this type of
concrete was chosen for the construction of the biological shield for the second experimental reactor in
Egypt. The study reveals that the ilmenite concrete under investigation is more effective for the attenuation
of fast neutrons. In addition the production of the hard capture secondary gamma rays have been greatly
decreased by eliminating the iron punchings from the constituents of the ilmenite concrete under
investigation which is also preferable from the economical point of view. Total macroscopic cross section
for fast neutrons, linear attenuation coefficients for gamma rays and the relaxation lengths both for the
whole energy range and at different energies have been obtained and comparison with other published
data has been done when it is available. Two empirical formulae have been derived which calculate the
total flux of fast neutrons and gamma rays for different types of concrete at different thicknesses. Good
agreement between measured and calculated values lIsing the two formulae has been obtained
