A general residue iteration method (the synthetic method) is described and applied to the solution of the neutron transport equation. For example, a synthesis of a sequence of solutions to diffusion equations each having a residue source can constitute such a solution. Only time independent systems consisting of isotropic scattering material of arbitrary geometry are considered herein. Exact solutions, approximate solutions, and the refinement of existing approximate methods can be accomplished within the framework of the synthetic method. (auth)
U.S. Atomic Energy Commission depository collection.
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DOE contract number: W-31-109-ENG-52 NSA number: NSA-17-005302 OSTI Identifier 4740270 Research organization: Knolls Atomic Power Lab., Schenectady, N.Y.