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A steady state solution for the one-dimensional energy dependent neutron transport equation in an infinite mediumBaker, Randal Scott, 1960- January 1988 (has links)
The one-dimensional energy dependent linear neutron transport equation has been solved for the case of constant cross sections in an infinite absorbing medium with the approximation of isotropic scattering in the laboratory frame of reference. The method of solution was to apply a Fourier transform with respect to space and a Laplace transform with respect to lethargy. The Laplace inversion is performed analytically, while the Fourier inversion is accomplished by a highly accurate algorithm employing a Hurwitz-Zweifel expansion in combination with an Euler-Knopp transformation and a Romberg quadrature routine. This method results in solutions accurate to four places which are suitable for benchmarks.
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Flux map and reactivity measurements in the TRIGA Mark 1 reactorCarmack, Charles William, 1947- January 1971 (has links)
No description available.
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Application of variational synthesis to solutions of multidimensional neutron transport problemsCobb, William Ronald 12 1900 (has links)
No description available.
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The Lattice Boltzmann Method applied to linear particle transport / Bernard ErasmusErasmus, Bernard January 2012 (has links)
In this study, the applicability of the Lattice Boltzmann Method to neutron transport is investigated.
The transport model used, is derived from the Boltzmann equation for neutral particles by inverting
the streaming operator and casting the integral transport equation into an operator form. From the
operator equation, an iterative solution to the transport problem is presented, with the first collision
source as the starting point for the iteration scheme. One of the main features of the method is the
simultaneous discretization of the phase space of the problem, whereby particles are restricted to
move on a lattice.
A full description of the discretization scheme is given along with the iterative procedure and
quadrature set used for the angular discretization. To mitigate lattice ray effects, an angular
refinement scheme is introduced to increase the angular coverage of the problem phase space.
The method is then applied to a model problem to investigate its applicability to neutron transport.
Three cases are considered where constant, linear and exponential interpolants are used to account
for the accumulation of flux due to the streaming of particles between nodes. The results obtained
are compared to a reference solution, that was calculated by using the MCNP code and to the values
calculated using a nodal SN method. Finally, areas of improvement are identified and possible
extensions to the algorithm are provided. / Thesis (MIng (Engineering Sciences in Nuclear Engineering))--North-West University, Potchefstroom Campus, 2013
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The Lattice Boltzmann Method applied to linear particle transport / Bernard ErasmusErasmus, Bernard January 2012 (has links)
In this study, the applicability of the Lattice Boltzmann Method to neutron transport is investigated.
The transport model used, is derived from the Boltzmann equation for neutral particles by inverting
the streaming operator and casting the integral transport equation into an operator form. From the
operator equation, an iterative solution to the transport problem is presented, with the first collision
source as the starting point for the iteration scheme. One of the main features of the method is the
simultaneous discretization of the phase space of the problem, whereby particles are restricted to
move on a lattice.
A full description of the discretization scheme is given along with the iterative procedure and
quadrature set used for the angular discretization. To mitigate lattice ray effects, an angular
refinement scheme is introduced to increase the angular coverage of the problem phase space.
The method is then applied to a model problem to investigate its applicability to neutron transport.
Three cases are considered where constant, linear and exponential interpolants are used to account
for the accumulation of flux due to the streaming of particles between nodes. The results obtained
are compared to a reference solution, that was calculated by using the MCNP code and to the values
calculated using a nodal SN method. Finally, areas of improvement are identified and possible
extensions to the algorithm are provided. / Thesis (MIng (Engineering Sciences in Nuclear Engineering))--North-West University, Potchefstroom Campus, 2013
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The theory of neutron wave propagation in partial fulfillment of the requirements for the degree of Doctor of Philosophy /Duderstadt, James J., January 1968 (has links)
Thesis (Ph. D.)--California Institute of Technology, 1968. / Also issued in print.
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Greuling-Goertzel calculations in heavy waterMack, Robert J. January 1959 (has links)
Thesis (M.S.)--University of Michigan, 1959.
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Neutron transport theory without azimuthal symmetry a research project submitted in partial fulfillment ... /Shultis, John Kenneth. January 1965 (has links)
Thesis (M.S.)--University of Michigan, 1965.
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A discussion of definitions, models, and interpretations employed in the measurement of diffusion lengths master's thesis submitted as a requirement ... /Latta, Andrew. January 1958 (has links)
Thesis (M.S.)--University of Michigan, 1958. / eContent provider-neutral record in process. Description based on print version record.
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The theory of neutron wave propagation in partial fulfillment of the requirements for the degree of Doctor of Philosophy /Duderstadt, James J., January 1968 (has links)
Thesis (Ph. D.)--California Institute of Technology, 1968. / eContent provider-neutral record in process. Description based on print version record.
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