Abstract
The authors report a highly efficient and accurate method for solving the transport equation in slab or sphere geometries. The complete information carried by the angular flux Ψ is rarely needed. In fact, to calculate reaction rates, leakage rates, etc., one needs only the zeroth and first moments of Ψ. The aim is to reduce the role of Ψ to a minimum. The basic assumption underlying the method is the local separability of the angular and energy dependence of Ψ within an energy group.
Original language | English |
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Title of host publication | Trans. Am. Nucl. Soc. (USA) |
Place of Publication | USA |
Publisher | American Nuclear Society |
Pages | 186 - 7 |
Volume | 24 |
State | Published - 1976 |
Bibliographical note
angular flux;local separability;energy dependence;one dimensional transport;eigenvalues;angular dependence;neutron transport;slab geometries;Keywords
- eigenvalues and eigenfunctions
- neutron transport theory
- numerical analysis