KINETIC AND BUCKLING MEASUREMENTS ON LATTICES OF SLIGHTLY ENRICHED URANIUM OR UO$sub 2$ RODS IN LIGHT WATER

Technical Report · Wed Jan 01 04:00:00 EST 1958

DOI:https://doi.org/10.2172/4328549· OSTI ID:4328549

Brown, J R; Harris, D R; Frantz, F S; Volpe, J J; Andrews, J C; Noordhoff, B H

Results of measurements made in the TRX critical facility on light water- moderated lattices of 1.3 and 1.15 wt.% enriched uranium metal fuel rods and of 1.3 wt.% enriched UO/sub 2/ fuel rods are described. Diameters of 0.60 in. and 0.39 in. for each fuel have been used as well as densities of 7.5 and 10.5 gm/cm/ sup 3/ for the UO/sup 2 fuel. Several water-touranium ratios have been investigated for each fuel rod type. Measurements have been made of radial and axial buckling, reflector savings, and temperature coefficient of reactivity. A migration area is inferred from the change of reactivity with change in either radial buckling or axial buckling. Anisotropy of migration area is determined from measurements of buckling on lattices of various height-todiameter ratios. (auth)

• Research Organization: Westinghouse Electric Corp. Bettis Plant, Pittsburgh
• Sponsoring Organization: US Atomic Energy Commission (AEC)
• DOE Contract Number: AT(11-1)-GEN-14
• NSA Number: NSA-12-009451
• OSTI ID: 4328549
• Report Number(s): WAPD-176
• Country of Publication: United States
• Language: English

Related Subjects

BUCKLING
CONFIGURATION
CRITICAL ASSEMBLIES
DENSITY
DISTRIBUTION
ENRICHMENT
FUEL ELEMENTS
MEASURED VALUES
METALS
NEUTRON FLUX
PHYSICS
REACTION KINETICS
REACTIVITY
REFLECTORS
RODS
TEMPERATURE
THICKNESS
TRX
URANIUM
URANIUM DIOXIDE
WATER MODERATOR