Browsing by Subject "Neutron transport theory"
Now showing items 1-9 of 9
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(Texas A&M University. Libraries, 1984)Analytic solutions of the multigroup space-time reactor kinetics equations are developed for a bare slab and spherical reactor, and a reflected slab and spherical reactor for the zero flux, the zero current, and the ...
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(Texas A&M University. Libraries, 1984)An approximate solution method has been developed to solve the one-dimensional, steady-state neutron transport problems in plane and spherical geometries. The spherical harmonics expansion and the multigroup approximation ...
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(Texas A&M University. Libraries, 1979)Angular singularities for the multigroup neutron diffusion equation are examined. Since the solution to this equation as well as the solution to other engineering equations of interest can exhibit unbounded derivatives at ...
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(Texas A&M University. Libraries, 1992)A method for applying the discrete ordinates method for solution of the neutron transport equation in arbitrary two-dimensional meshes has been developed. The finite difference approach normally used to approximate spatial ...
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(Texas A&M University. Libraries, 1985)High order numerical solutions of the time-dependent one speed neutron transport equation are developed using cubic hermite polynomial trial functions, variational techniques, and exponential matrix operators. Two new ...
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(Texas A&M University. Libraries, 1992)In this work, we apply a recently developed theory, information-based complexity, to numerical transport theory. Two classes of information, cell-average information and point-evaluation information, and two popular ...
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(Texas A&M University. Libraries, 1977)A nuclear data library has been created for medium energy neutron transport calculations. The 60-group library includes P5 cross sections in standart LASL format for H, B, C, N, O, Si, Fe and W. The 60-group structure was ...
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(Texas A&M University. Libraries, 1977)The angular singularities of the multigroup neutron diffusion equations are studied. The solution of the diffusion equations may have unbounded derivatives at points where the boundary has a corner, where two material ...
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(Texas A&M University. Libraries, 1982)A new numerical method is developed to solve the multigroup steady state neutron transport equation in P(,N) approximation in one dimensional slab and spherical geometry. The multigroup P(,N) moment equations are transformed ...