Neutron flux measurements on a mock-up of a storage cask for high-level nuclear waste using 2.5 MeV neutrons

In this study, a neutron generator (NG) producing neutrons
of 2.5 MeV was employed to simulate neutrons produced in spent nuclear fuel. Different
configurations of shielding layers of steel and polyethylene were positioned between the target of
the NG and a NE-213 detector. The results of the measurements of neutron and γ radiation and the
corresponding simulations with the code MCNP6 are presented. Details of the experimental set-up as
well as neutron and photon flux spectra are provided as reference points for such NG investigations
with shielding structures.

Source: Journal of Radiological Protection - June 6, 2018 Category: Physics Authors: H Saur í Suárez, F Becker, A Klix, B Pang and T Döring Source Type: research