Browsing by Subject "Neutron Transport"
Now showing items 1-7 of 7
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(2012-02-14)In this dissertation, we discuss an adaptive angular discretization scheme for the neutral-particle transport equation in three dimensions. We mesh the direction domain by dividing the faces of a regular octahedron into ...
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(2016-07-28)The accurate modeling of complex physical phenomena, such as radiation transport in a laboratory experiment or a nuclear reactor, challenges the limits of modern computing resources and helps drive the requirement for ...
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(2015-12-01)The standard multigroup (MG) method for energy discretization of the transport equation can be sensitive to approximations in the weighting spectrum chosen for cross-section averaging. As a result, MG often inaccurately ...
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(2013-03-14)In this thesis we investigate coupling and preconditioning techniques for 19D hybrid neutronics calculations. Each problem is represented by two spatial regions with Sn in one region and either Diffusion (P1) or P3 in the ...
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(2017-07-27)In this dissertation we present advances to the nonlinear diffusion acceleration for void regions using second order forms of the transport equation. We consider the weighted least-squares and the self-adjoint angular flux ...
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(2015-05-04)In this dissertation we detail the development, implementation, and testing of a new cut-cell discretization for the discrete ordinates form of the neutron transport equation. This method provides an alternative to ...
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(2022-04-20)The purpose of this thesis is to detail the analysis on the stability and effectiveness of a DSA scheme having two diffusion cells per transport cell. The inspiration to look into such a scheme originated from Ryosuke ...