Neutron yield using a semi-Monte Carlo simulating method for D-T fusion neutron sources

•Semi-MC method based on the finite element analysis to extend Multiphysics coupling•Deuteron transport simulation simplified with the continuous-slowing down approximation and the nuclear multiple scattering•Good agreement with the results of the experiment and GEANT4•Greatly improved calculation efficiency Neutron yield and spatial distribution are crucial parameters of a gaseous target D-T neutron source. The exact calculation of these parameters in large-size geometries with complex fluid dynamics is very important for gaseous target neutron source design and subsequent applications. The gaseous target on operating conditions put more requirements on the Multiphysics simulating method. The fusion neutron yield simulating method has been developed using semi-Monte Carlo based on the finite element analysis for Multiphysics. The method has been verified using the model of a D-T fusion neutron source with a windowless gas target and compared with experimental results and the GEANT4 simulations. Compared with the experimental results, the simulated neutron yield error is 8.31%, and compared with the result of GEANT4, the relative error of total neutron yield is 3.34%. The spatial distributions of neutron yield are in good agreement with the results of GEANT4. In particular, the computing time is reduced from ∼200 core-hours with GEANT4 to ∼50 core-hours with the developed semi-Monte Carlo method, greatly improving the calculation efficiency.