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2DF is a two-dimensional, multigroup program written in FORTRAN for solving the neutron transport equation using the SN method. The program can determine the real or adjoint solution for x-y, r-z, or r-theta geometry. Isotropic, or a form of linear anisotropic, scattering may be considered. Various boundary conditions are allowed. The program also contains a number of search options whereby one can vary dimensions or concentrations to arrive at a predetermined eigenvalue. A distributed source may be specified. A library of cross sections is available on magnetic tape. Cross sections may be read from the library tape and/or from cards. Storage restrictions are specified by a complicated equation involving SN order, number of materials, mesh intervals, and energy groups, and specified boundary conditions. (ERA citation 08:022430)...Software Description: UNIVAC1108; FORTRAN V; EXEC8.