Evaluation of neutron and gamma dose in a new deuterium-deuterium fusion neutron generator facility using MCNP and experimental methods

Abstract

A deuterium-deuterium (D-D) neutron generator facility has been developed with a wide range of applications in mind. D-D neutron generators provide a safe, convenient, and low-cost solution for the production of thermal, epithermal, and fast neutrons for laboratory and industrial applications. The regulatory burden for operating one of these generators is small as it contains no radioactive material and produces no radiation when turned off. One such D-D neutron generator has been installed at the National Center of Nuclear Sciences and Technologies (CNSTN). This generator produces 2.45 MeV fast neutrons with a maximum yield of 10¹⁰.n/s. To maintain a strong radiation safety program, detailed knowledge of the radiation dose rates around the neutron generator is crucial for ensuring the radiological protection of the personnel involved with its operation. This work describes the Monte Carlo calculations and experimental measurements carried out in the Neutron Generator facility of the CNSTN. The adequacy of the radiation shielding of the facility was verified by measuring the neutron and gamma dose rates at various locations inside and outside the neutron generator hall during operation and comparing them with Monte Carlo calculations. Measured and calculated dose rates were in agreement to better than 20% depending on location. The operation of this neutron facility will provide a suitable neutron source for future basic and applied research.

Keywords: DD neutron generator; Dose rate; MCNP; Neutron shield.