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Showing 1 to 7 of 7 for “"neutron diffusion equation"”.
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Lie group invariant finite-difference schemes for the neutron diffusion equation
… are used to solve a variety of differential equations. For the neutron diffusion equation, the typical local truncation error for standard finite difference approximation is on the order of the mesh spacing squared. To improve the accuracy of the finite difference approximation of the …
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Higher Order Nodal Methods for Solving the Steady-State Neutron Diffusion Equation
Made available in DSpace on 2017-07-06T18:55:59Z (GMT). No. of bitstreams: 3 Rajic_Hrabri_L_MS.pdf: 30908896 bytes, checksum: 49031fbb5ce3965a84550e8ed6a14c67 (MD5) Rajic_Hrabri_L_MS_ABS.pdf: 500847 bytes, checksum: dd84aaf9af22b9252ed2a0353a415f57 (MD5) license.txt: 4813 bytes, checksum: …
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Derivation of Similarith solutions for the One-Dimensional, One-Velocity Neutron Diffusion Equation Using Lie Group Transformation Theory
Made available in DSpace on 2017-07-06T18:55:28Z (GMT). No. of bitstreams: 3 Myers_William_L_MS.pdf: 26862151 bytes, checksum: fb1b194ae8d1df514a990af341ae3487 (MD5) Myers_William_L_MS_ABS.pdf: 596542 bytes, checksum: 6959b7aaf4a682d0c3b55423a0f04de3 (MD5) license.txt: 4813 bytes, checksum: …
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Application of Lie Groups to Discretizing Nuclear Engineering Problems
… in one dimension for the time-independent neutron diffusion equation for Cartesian, cylindrical, and spherical geometries. This method will be expanded to constructing two-term recurrence relations for an arbitrary number of spatial regions, as well as detailing starting point values for …
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An application of Chebyshev polynomials to the solution of a two-dimensional elliptic boundary-value problem
… to approximate solutions to the two-dimensional neutron diffusion equation. The two-dimensional two-group neutron diffusion equations are solved by expanding neutron fluxes in a finite series of Chebyshev polynomials over large regions of a fission reactor. All the equations for the expansion …
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A reactor physics framework to detect anomalies in HTGR core
This dissertation extends the application of neutron noise analysis as a tool for detecting anomalies in High Temperature Gas-cooled Reactors (HTGRs). Neutron noise is defined as the fluctuations in the neutron detector signal caused by perturbations in a nuclear reactor. Neutron noise analysis is …
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Three dimensional heterogeneous finite element method for static multi-group neutron diffusion
Because current full-core neutronic-calculations use two-group neutron diffusion and rely on homogenizing fuel assemblies, reconstructing pin powers from such a calculation is an elaborate and not very accurate process; one which becomes more difficult with increased core heterogeneity. A …