Neutron and gamma-ray shielding design for a 30Ci (1.11TBq) 241Am-Be irradiation facility is studied using MCNP5 Monte Carlo simulation code. The study focuses on the optimization of the shielding layers of the previously planned neutron irradiation facility. The shielding design aims at reducing the effective dose rate down to 10μSv/h for occupationally exposed workers as recommended by the International Commission on Radiological Protection (ICRP) (20mSv per year for workers). The dose rate calculations consider not only 241Am-Be produced neutrons but also gamma rays from the 241Am decay, 12C∗ de-excitation, and neutron interaction with source and facility materials. Different materials (paraffin, borated-paraffin, beryllium, copper, tantalum, tungsten, zinc, bismuth, and lead) have been investigated as neutron and gamma shields. The choice of the shielding materials is based on their effectiveness (the total weight of the facility and the cost). Among several configurations, shielding layers consisting of 10cm paraffin wax, 2.5cm lead, and 31.5cm borated-paraffin wax are found sufficient to meet the safety requirements, leading to a cubic facility of 104.2cm overall length. Some irradiation parameters are estimated for the final design; namely neutron and gamma spectra as well as flux and absorbed dose components. In addition, the occupational exposure is assessed considering ICRP exposure conditions to calculate the effective dose rate along with the isodose distribution.
Read full abstract