This report is intended as a User's Manual for SWAN''--- a code written for perturbation theory analysis and optimization of the nucleonic characteristics of fusion reactor blankets. SWAN is also applicable to any problem described by the inhomogeneous linear transport equation, e.g., radiation shield problems. The optimization method is based on variational techniques. The variables of the optimization are material densities, with no restriction on their number. One joint restraint may be imposed in addition to upper and lower limits on each density. The parameter to be extremized and the restraint may be either a weighttype (linear) or nucleonic (bilinear) ...
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This report is intended as a User's Manual for SWAN''--- a code written for perturbation theory analysis and optimization of the nucleonic characteristics of fusion reactor blankets. SWAN is also applicable to any problem described by the inhomogeneous linear transport equation, e.g., radiation shield problems. The optimization method is based on variational techniques. The variables of the optimization are material densities, with no restriction on their number. One joint restraint may be imposed in addition to upper and lower limits on each density. The parameter to be extremized and the restraint may be either a weighttype (linear) or nucleonic (bilinear) functional. The transport calculations for SWAN are performed with the one-dimensional discrete-ordinate code ANISN. (auth)
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Greenspan, E.; Price, W. G., Jr. & Fishman, H.SWAN: a code for the analysis and optimization of fusion reactor nucleonic characteristics,
report,
November 1, 1973;
Princeton, New Jersey.
(digital.library.unt.edu/ark:/67531/metadc1022818/:
accessed April 22, 2018),
University of North Texas Libraries, Digital Library, digital.library.unt.edu;
crediting UNT Libraries Government Documents Department.