Neutron Flux Distributions in the Materials Testing Reactor. Part II. The 5 x 5 Loading,
Abstract
Flux distribution measurements have been made in the Materials Testing Reactor with the fuel elements arranged in a Symmetrica1 5 x 5 loading. Three-dimensional thermal neutron flux distribution maps were made for both clean, cold fuel elements and depleted, poisoned fuel elements. The data are presented as a series of relative activity curves and as a set of absolute flux maps. A qualitative comparison of the flux distribution is made between the 5 x 5 loading and the 3 x 9 north slab loading.
Document Details
- Document Type
- Technical Report
- Publication Date
- Nov 17, 1953
- Accession Number
- ADA321721
Entities
People
- G. O. Bright