Measurement and calculation of the neutron spectrum and gamma dosimetry of the fast neutron device at Xi’an Pulse Reactor

The neutron spectrum and neutron fluence of a fast neutron device at Xi’an Pulse Reactor were measured with multiple foil activation method and calculated with Monte Carlo technique in the paper. Thermo-luminescence detector (TLD) (7LiF(Mg,Ti)-1007M) is used to measure gamma dosimetry of the device. The experimental result proves that the goal of the design is achieved.