An integrated simulation study of a compact accelerator-based neutron source

The Prototype Canadian Compact Accelerator-based Neutron Source (PC-CANS) is a national initiative led by the University of Windsor in collaboration with TRIUMF, Canadian Nuclear Laboratories (CNL), and other Canadian partners to establish a versatile, non-fission neutron source (based on p to n conversion) for research, training, and some academic and industrial applications. This paper presents CNL’s contributions to the design effort, providing an integrated, simulation-based assessment covering neutron production, thermal-hydraulic performance, radiation shielding, and prospective applications. The four analyses use a common source configuration so that neutronic results define the source term, thermal-hydraulic and shielding calculations test the operating envelope, and the instrument concepts translate the results into preliminary design requirements. Monte Carlo N-Particle (MCNP) modelling was used to characterize neutron production from a 10 MeV, 0.7 mm beryllium target with multiple reflector and moderator configurations, including time-dependent neutron pulse profiles. Thermal-hydraulic simulations using the AlgoRIthm for Analysis of Network Thermalhydraulics (ARIANT) code were carried out to quantify steady-state and pulsed temperature margins for the water-cooled target. Shielding calculations were performed to optimize combinations of high-density polyethylene, borated polyethylene, and lead to satisfy ambient dose-equivalent limits for several currents cases. Finally, conceptual designs for a Small Angle Neutron Scattering (SANS) instrument, a neutron diffraction/imaging multipurpose instrument, and irradiation stations are discussed. Together, the results provide an integrated preliminary design basis for PC-CANS and identify the principal requirements for detailed engineering.