Gamma Unfolding for Poly Boron (PB), Heavy Concrete (HC), Single Shields and Multilayers Containing Poly Boron Shield

The gamma ray spectrum obtained from a 3.7 × 104 Bq 252Cf source after passing through different shielding materials at different thicknesses and different arrangements were detected with a NaI (Tl) detector was fed to a computerized MCA to have a spectrum. After that, it was folded up and stored. For each of the shielding arrangements under study, the unfolded dose spectra of the fission gamma ray spectrum of the 252Cf source were also measured. Using the three-dimensional Monte Carlo computer code MCNP for fission gamma rays, theoretical calculations have been carried out to investigate the features of the shielding configurations stated above. The values gained through experimentation are then compared with these. The understanding is quite good. Calculations of gamma ray fluxes and associated doses have also been made. The investigation's goal was to ascertain the materials' and their multilayers' efficacy as gamma ray shields. The materials (both single layer and multilayer) examined have proven to be quite effective as a gamma ray shield. Shielding experiments results for gamma ray transmission have been compared with the calculations using MCNP code on PB and HC. In the present work, the 252Cf source, has been chosen as it emits gamma rays with different energies and intensities. Hence it was necessary to identify the components of the gamma rays, and a part of the present work is devoted to three energy bins, namely, 25, 50 and 100 keV, this aspect of unfolding study of gamma rays was evaluated.