Neutron Transport Calculations in Cylindrical Geometry
- 1 June 1984
- journal article
- research article
- Published by Taylor & Francis in Nuclear Science and Engineering
- Vol. 87 (2) , 107-112
- https://doi.org/10.13182/nse84-a17705
Abstract
An integral transformation technique and the FN method are used to solve, for the case of isotropic scattering, the albedo problem and the internal-source problem relevant to neutron transport theory for a bare cylinder of infinite length. The neutron flux distribution and the neutron current distributions are found with five or six figures of accuracy and are tabulated for selected illustrative cases. In addition, selected results for the albedo are reported with an accuracy of eight to ten significant figures.Keywords
This publication has 4 references indexed in Scilit:
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- On Angular Flux Computations in Neutron-Transport TheoryNuclear Science and Engineering, 1982
- The FN Method in Neutron-Transport Theory. Part I: Theory and ApplicationsNuclear Science and Engineering, 1979
- Elementary solutions of the transport equation and their applicationsAnnals of Physics, 1960