Barite concrete-based cement composites for ²⁵²Cf spontaneous neutron and ⁶⁰Co/¹⁹²Ir shielding based on Monte Carlo computation

Abstract Barite concrete composite materials have been investigated for 252 Cf spontaneous neutron and 60 Co/ 192 Ir gamma sources’ shielding using Monte Carlo computational method. The Particle Heavy Ion Transport code System (PHITS) was used to compute the properties of three different (barite concrete, barite cement, aggregate) as structural walls in fixed & industrial radiography Non-Destructive Testing applications. obtained results displayed good neutrons emitted from source, effective dose drops about 10 8 times only 140 cm wall thickness, it found be more than other investigated. In addition, showed a relatively smaller thickness compared ordinary concrete. decision-making process based on ALARA principle limitation that use such facilities is cement aggregate, both design. To achieve an average value 1 μ Sv/h, result shows 80 needed, while 125 130 aggregate are respectively shield Co-60 source. Meanwhile, 50 made sufficient cut down rate Sv/h (for Ci 55 150 Ir), which appropriate design public area adjacent radiographic facility. It therefore concluded data most material radioactive sources ( Co, Ir, Cf)