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Calculation of Group Cross Sections for Hot Monoatomic Moderator with Variable Flux Weighting Within Groups 704 Code 521/RE 145
註釋This code finds inelastic cross-section matrix elements (transfer matrix) for hot monatomic moderator for multi-group calculations by numeric- analytic double integration of Cohen's formula. Several approximations to the actual neutron density can be used as weight functions over the velocities of the initial groups. Modified and supplemented results are presented on binary cards and/or tape for direct input into the Argonne Transport Theory Codes or the SNG Code, or for offline output.