Abstract:

The source expansion neutron transport discrete ordinates method expresses the solution of differential form discrete ordinates by a sum of polynomial form particular solution and exponential function homogeneous solution. The incoming angular neutron flux can be used as boundary condition to determine the coefficients of homogeneous solution. The particular solution can be obtained directly with source expansion coefficients. Finally, the hexagonal neutron transport equation can be solved with source iteration. Discrete ordinates method normally converges slow and can be accelerated with coarse mesh finite method (CMFD). Numerical results indicates that eigenvalues and power distributions of the reference problems agrees well with reference results. The CMFD acceleration method achieves more than 20 times speedup in the study.

Key words: hexagonal, discrete ordinates, source expansion, acceleration