A One-Dimensional Few-Group Diffusion Code Package for Fast and Intermediate Reactors.
AIR FORCE INST OF TECH WRIGHT-PATTERSON AFB OH SCHOOL OF ENGINEERING
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Three computer codes have been written to provide a complete package with which one-dimensional few group diffusion calculations may be performed for fast and intermediate reactors. Two sixteen-group microscopic cross-section decks ANL and LASL are maintained on punched cards withe the codes. IMX collapses the sixteen-group microscopic cross-sections over zero-moment calculated spectra. FMX collapses the sixteen-group cross-sections over multigroup diffusion calculated spectra. ONEDIF performs eigenvalue searches on geometry and composition. Author
- Computer Programming and Software
- Fission Reactor Physics