An Optimization of Shielding Design for Compact-Fusion Neutron Sources

The Compact-Fusion Neutron Source (C-FNS) is widely used in various industrial and research area such as neutron activation analysis, neutron radiography, neutron capture therapy, and so on. Also, for easier and wider applications of C-FNS, a need for more compact and even portable design is being increased. To achieve a goal of C-FNS design considering its compactness, optimization of neutron and gamma shielding is essential. In this study, an optimized shielding design for deuterium-deuterium (D-D) C-FNS was performed based on the well-known MCNP6 code. In this paper, optimized moderator and shield design was suggested based on a simple 1-D spherical model. The 15cm-thickness polyethylene moderator was suggested with 45cm-thickness polyethylene neutron shield and 20cm-thickness lead photon shield for 1011 D-D neutron source. In addition, minimum shield thickness was also evaluated for the various strength of D-D neutron sources.