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On the Build-Up Factor from the Multi-Group Neutron Diffusion Equation with Cylindrical Symmetry
DepartmentofAppliedMath, Universidade Federal do Rio Grande do Sul, Porto Alegre, Brazil
DepartmentofAppliedMath, Universidade Federal do Rio Grande do Sul, Porto Alegre, Brazil
DepartmentofAppliedMath, Universidade Federal do Rio Grande do Sul, Porto Alegre, Brazil
DepartmentofAppliedMath, Universidade Federal do Rio Grande do Sul, Porto Alegre, Brazil
- 1 DepartmentofAppliedMath, Universidade Federal do Rio Grande do Sul, Porto Alegre, Brazil
- 2 DepartmentofAppliedMath, Universidade Federal do Rio Grande do Sul, Porto Alegre, Brazil
- 3 DepartmentofAppliedMath, Universidade Federal do Rio Grande do Sul, Porto Alegre, Brazil
- 4 DepartmentofAppliedMath, Universidade Federal do Rio Grande do Sul, Porto Alegre, Brazil
World Journal of Nuclear Science and Technology·Volume 03 (2013)·Pages 1–5·Published 29 January 2013·DOI10.4236/wjnst.2013.31001
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Abstract
We consider the time dependent neutron diffusion equation for one energy group in cylinder coordinates, assuming translational symmetry along the cylinder axis. This problem for a specific energy group is solved analytically applying the Hankel transform in the radial coordinate r . Our special interest rests in the build-up factor for a time dependent linear neutron source aligned with the cylinder axis, which in the limit of zero decay constant reproduces also the static case. The new approach to solve the diffusion equation by integral transform technique is presented and results for several parameter sets and truncation in the solution for the flux and build-up factor are shown and found to be compatible to those of literature [1,2].
KeywordsBuild-Up FactorCylindrical GeometryHankel Transform
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