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  • Binary stochastic media transport : a coupled mesh based method

    Creator:
    Barnett, Nathan A.
    Abstract:
    Transport in a binary stochastic media has been an area of interest for many applications over the past three decades. Many different methods have been attempted, most based on the Levermore-Pomraning coupled transport model. However, this method has never been able to correctly solve problems where a large amount of...
    Resource Type:
    Masters Thesis
    Full Text:
    Levermore-Pomraning coupled transport model. However, this method has never been able to correctly solve

  • Analysis of the method of tubes characteristic schemes in the thick diffusive limit

    Creator:
    Rising, Michael E.
    Abstract:
    Characteristic methods are widely known to be very accurate approaches to the solution of numerical transport problems. These methods are most often used for neutron transport applications (i.e. lattice physics calculations) where spatial cells are of intermediate optical thickness (O(1) - O(100) mean free paths, depending on the energy group)...
    Resource Type:
    Masters Thesis
    Full Text:
    Characteristic methods are widely known to be very accurate approaches to the solution of numerical transport

  • An assessment of a mesh-based method for slab-geometry transport in stochastic materials

    Creator:
    Bassett, Brody R.
    Abstract:
    There exists a variety of methods to solve the radiation transport equation in stochastic materials, including the Levermore-Pomraning method and the atomic mix method, each of which is designed to replicate the results given by benchmarks with materials rearranged in a randomized fashion. While the atomic mix method is very...
    Resource Type:
    Masters Thesis
    Full Text:
    transport. The atomic mix model can have large errors, as stochastic e�ects such as the likelihood of

  • Solution of the 2D quasi-diffusion low-order equations using a coupled nodal/finite volume discretization in Cartesian and hexagonal geometry

    Creator:
    Nes, Razvan
    Abstract:
    An important improvement in the area of reactor core neutronic modeling is the development and use of the methods based on "quasi-diffusion" (QD) low-order equations. This family of methods takes into account the transport exactly using "functionals" computed by solving transport equations, and is amenable to solution with a variety...
    Resource Type:
    Dissertation
    Full Text:
    methods takes into account the transport exactly using “functionals” computed by solving transport

  • A comparative study of nodal course-mesh methods for pressurized water reactors

    Creator:
    Bukar, Kyari Abba
    Abstract:
    Several computer codes based on one and two-group diffusion theory models were developed for SHUFFLE. The programs were developed to calculate power distributions in a two-dimensional quarter core geometry of a pressurized power reactor. The various coarse-mesh numerical computations for the power calculations yield the following: the Borresen's scheme applied...
    Resource Type:
    Masters Thesis
    Full Text:
    model have quite attractive features. A Comparative Study of Nodal Coarse-Mesh Methods for

  • Extending the discrete maximum principle for the IMC equations

    Creator:
    Talbot, Paul W.
    Abstract:
    The implicit Monte Carlo (IMC) method [16] for radiative transfer, developed in 1971, provides numerical solutions to the tightly-coupled, highly-nonlinear radiative heat transfer equations in many physical situations. Despite its popularity, there are instances of overheating in the solution for particular choices of time steps and spatial grid sizes. To...
    Resource Type:
    Masters Thesis
    Full Text:
    radiation transport. While she undoubtedly deserves first mention, certainly the first individual

  • An advanced nodal discretization for the quasi-diffusion low-order equations

    Creator:
    Nes, Razvan
    Abstract:
    The subject of this thesis is the development of a nodal discretization of the low-order quasi-diffusion (QDLO) equations for global reactor core calculations. The advantage of quasi-diffusion (QD) is that it is able to capture transport effects at the surface between unlike fuel assemblies better than the diffusion approximation. We...
    Resource Type:
    Masters Thesis
    Full Text:
    capture transport effects at the surface between unlike fuel assemblies better than the diffusion

  • Neutron transport benchmarks for binary stochastic multiplying media : planar geometry, two energy groups

    Creator:
    Davis, Ian M. (Ian Mack)
    Abstract:
    Benchmark calculations are performed for neutron transport in a two material (binary) stochastic multiplying medium. Spatial, angular, and energy dependence are included. The problem considered is based on a fuel assembly of a common pressurized water nuclear reactor. The mean chord length through the assembly is determined and used as...
    Resource Type:
    Masters Thesis
    Full Text:
    equations. Pomraning named this the "Interface" model. Solving these four transport equations results in a