A One-Dimensional Few-Group Diffusion Code Package for Fast and Intermediate Reactors.
Abstract
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)
Document Details
- Document Type
- Technical Report
- Publication Date
- Jun 01, 1970
- Accession Number
- AD0875371
Entities
People
- Dale W. Shosa
Organizations
- Air Force Institute of Technology