DRYDIFF-2 - a Code for the Solution of Few-group Diffusion Equation in One Dimension with General Albedo-type Boundary Conditions PDF Download
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Author: Iván Lux
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Languages : en
Pages : 14
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Author: Iván Lux
Publisher:
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Category :
Languages : en
Pages : 14
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Category : Nuclear energy
Languages : en
Pages :
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Category : Nuclear reactors
Languages : en
Pages : 50
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Author: Orville J. Marlowe
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Category : Diffusion
Languages : en
Pages : 80
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Category : Technology
Languages : en
Pages : 966
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Category : Government publications
Languages : en
Pages : 1096
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Category : Government reports announcements & index
Languages : en
Pages : 1088
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Author: Liaqat Ali Khan
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Category :
Languages : en
Pages : 206
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Category :
Languages : en
Pages :
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EQUIPOISE-3 is an IBM-7090 FORTRAN programmed code for the solution of two-group, two-dimensional, neutron diffusion equations. A maximum of 2l00 mesh points may be used, and the code will solve problems in either rectangular or cylindrical geometry. Logarithmic derivative boundary conditions are allowed, and removal of neutrons from both groups is permitted. Adjoint fluxes with the associated fluxadjoint flux regional integrals may be calculated automatically if desired. A constant buckling, group-dependent buckling, or region-dependent buckling may be specified for rectangular geometry. This program is intended to fill the need for a rapid two-dimensional calculation suitable for survey calculations. During the iterative part of the computations, all operations are carried out in the core memory. The magnetic tape memory is used only for input, output, and program storage. The running time for a 1000-point problem requiring 100 iterations would be about 3 min.(auth).
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Languages : en
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WHIRLAWAY is an IBM 7090 FORTRAN programmed code for the solution of two- group neutron diffusion equations in xyz geometry. The code was designed to run under control of the IBM 7090 FORTRAN Monitor System on a machine with at least six tape units. The maximum number of mesh points is limited to 12,750. Arbitrary distributions of materials and mesh spacing are permitted. The boundary conditions are either zero flux or zero current at each of the six faces of the reactor, and the code will, if desired, compute the adjoint-flux and associated flux-adjoint-flux region integrals that are necessary for perturbation calculations. Computation time is approximately 0.006 sec per point iteration. Normally, running times are about 2 to 3 hr for a 10,000-point problem. (auth).
