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VENTURE: a code block for solving multigroup neutronics problems applying the finite-difference diffusion-theory approximation to neutron transport

Description: The computer code block VENTURE, designed to solve multigroup neutronics problems with application of the finite-difference diffusion-theory approximation to neutron transport (or alternatively simple P$sub 1$) in up to three- dimensional geometry is described. A variety of types of problems may be solved: the usual eigenvalue problem, a direct criticality search on the buckling, on a reciprocal velocity absorber (prompt mode), or on nuclide concentrations, or an indirect criticality search on … more
Date: October 1, 1975
Creator: Vondy, D.R.; Fowler, T.B. & Cunningham, G.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Acceleration techniques for response matrix methods

Description: Application of the power iteration method to the multigroup response matrix equations reduces them to a series of one-group problems. Applying acceleration techniques to each of these monoenergetic problems results in substantial reductions in computational effort. The use of point over-relaxation methods in the solution of these equations is described. Over-relaxation is also applied to the outer-iteration eigenvalue and source estimations with considerable success. 10 references. (auth)
Date: January 1, 1975
Creator: Sicilian, J. M. & Pryor, R. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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