Accession Number:

AD0875371

Title:

A One-Dimensional Few-Group Diffusion Code Package for Fast and Intermediate Reactors.

Descriptive Note:

Master's thesis,

Corporate Author:

AIR FORCE INST OF TECH WRIGHT-PATTERSON AFB OH SCHOOL OF ENGINEERING

Personal Author(s):

• Shosa, Dale W.

Report Date:

1970-06-01

Pagination or Media Count:

252.0

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

Descriptors:

• (*NEUTRON TRANSPORT THEORY
• COMPUTER PROGRAMS)
• NEUTRON FLUX
• NEUTRON SPECTRUM
• CRITICAL ASSEMBLIES
• NEUTRON CROSS SECTIONS
• DIFFERENCE EQUATIONS
• INTEGRAL EQUATIONS
• MATRICES(MATHEMATICS)
• CONVERGENCE
• FAST REACTORS
• GROUPS(MATHEMATICS)
• TABLES(DATA)

Subject Categories:

• Computer Programming and Software
• Fission Reactor Physics

Distribution Statement:

APPROVED FOR PUBLIC RELEASE