HALLAM EXPONENTIAL EXPERIMENTS USING U-Mo FUEL

Technical Report · Fri Sep 15 04:00:00 EDT 1961

DOI:https://doi.org/10.2172/4840854· OSTI ID:4840854

Hillig, O R

The results of exponential experiments with graphitemoderated lattices containing multirod fuel clusters are presented. Three lattices of different spacings where the fuel clusters form regular hexagons, and one square lattice were studied. Fuel clusters were of a uranium molybdenum alloy. Some measurements were also made using a single uranium carbide fuel cluster and a uranium molybdenuan fuel element of lower U/sup 235/ enrichment. The results are presented for measurements of thermal neutron diffusion length (L) of the moderator in each assembly, material buckling (B2) for the various lattices, detailed neutron flux distributions, thermal utilization, (f) and the ratios involved in resonance escape probability (r/sub P/) and fast effect (r/sub - (auth)>i

• Research Organization: Atomics International. Div. of North American Aviation, Inc., Canoga Park, Calif.
• DOE Contract Number: AT(11-1)-GEN-8
• NSA Number: NSA-15-030259
• OSTI ID: 4840854
• Report Number(s): NAA-SR-6118
• Country of Publication: United States
• Language: English

Related Subjects

BUCKLING
CONFIGURATION
DIFFUSION LENGTH
DISTRIBUTION
ENRICHMENT
EXPONENTIAL PILES
FAST FISSION FACTOR
FUEL ELEMENTS
FUELS
GRAPHITE MODERATOR
HNPF
MEASURED VALUES
MOLYBDENUM ALLOYS
NEUTRON FLUX
REACTOR TECHNOLOGY
RESONANCE ESCAPE PROBABILITY
THERMAL NEUTRONS
THERMAL UTILIZATION
URANIUM ALLOYS
URANIUM CARBIDES
VARIATIONS