A fully coupled Monte Carlo/discrete ordinates solution to the neutron transport equation.
AuthorBaker, Randal Scott.
AdvisorFilippone, William L.
MetadataShow full item record
PublisherThe University of Arizona.
RightsCopyright © is held by the author. Digital access to this material is made possible by the University Libraries, University of Arizona. Further transmission, reproduction or presentation (such as public display or performance) of protected items is prohibited except with permission of the author.
AbstractThe neutron transport equation is solved by a hybrid method that iteratively couples regions where deterministic (S(N)) and stochastic (Monte Carlo) methods are applied. Unlike previous hybrid methods, the Monte Carlo and S(N) regions are fully coupled in the sense that no assumption is made about geometrical separation or decoupling. The hybrid method provides a new means of solving problems involving both optically thick and optically thin regions that neither Monte Carlo nor S(N) is well suited for by themselves. The fully coupled Monte Carlo/S(N) technique consists of defining spatial and/or energy regions of a problem in which either a Monte Carlo calculation or an S(N) calculation is to be performed. The Monte Carlo region may comprise the entire spatial region (with vacuum boundary conditions) for selected energy groups, or may consist of a rectangular areas that is either completely or partially embedded in an arbitrary S(N) region. The Monte Carlo and S(N) regions are then connected through the common angular boundary fluxes, which are determined iteratively using the response matrix technique, and volumetric sources. The hybrid method has been implemented in the S(N) code TWODANT by adding special-purpose Monte Carlo subroutines to calculate the response matrices and volumetric sources, and linkage subroutines to carry out the interface flux iterations. The common angular boundary fluxes are included in the S(N) code as interior boundary sources, leaving the logic for the solution of the transport flux unchanged, while, with minor modifications, the diffusion synthetic accelerator remains effective in accelerating the S(N) calculations. The special-purpose Monte Carlo routines used are essentially analog, with few variance reduction techniques employed. However, the routines have been successfully vectorized, with approximately a factor of five increase in speed over the non-vectorized version. The hybrid method is capable of solving forward, inhomogeneous source problems in X - Y and R - Z geometries. This capability includes multigroup problems involving upscatter and fission in non-highly multiplying (k(eff) ≤ .8) systems. The hybrid method has been applied to several simple test problems with good results.
Degree ProgramNuclear and Energy Engineering