Experimental Bucklings of Heavy Water Moderated Lattices of Natural Uranium Metal Rod Clusters

Journal Article · Wed Feb 28 23:00:00 EST 1962 · Nuclear Science and Engineering

OSTI ID:4803798

Hurley, Jr., T. J. ^[1]; Fike, H. R. ^[1]; O'Neill, G. F. ^[1]

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1. Du Pont de Nemours (E.I.) and Co., Aiken, SC (United States). Savannah River Laboratory

Studies performed in the Process Development Pile of the Savannah River Laboratory provide precise measurements of the material bucklings of a number of D₂O moderated lattices of natural uranium metal rods over an extended range of fuel assembly sizes and lattice pitches. The 1-in. uranium rods are clad with 0.032 in. of aluminum. Fuel assembly sizes vary from single rods to clusters of 3, 7, and 19 rods (0.09 to 1.81 kg U/cm) and lattice spacings from 7.00 to 21.00 in., covering a range of moderator-to-fuel volume ratios from 10.23 to 161.53. A few lattices are studied at different D₂O purities, in loadings of different sizes, and in reflected loadings.

• Research Organization: Du Pont de Nemours (E.I.) and Co., Aiken, SC (United States). Savannah River Laboratory
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
• DOE Contract Number: AC09-76SR00001
• NSA Number: NSA-16-012683
• OSTI ID: 4803798
• Journal Information: Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Vol. 12; ISSN 0029-5639
• Publisher: Taylor & Francis
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ALUMINUM
BUCKLING
CANNING
CONFIGURATION
DENSITY
ERRORS
FUEL ELEMENTS
FUELS
HEAVY WATER MODERATOR
IMPURITIES
MEASURED VALUES
MODERATORS
NATURAL URANIUM FUEL
NEUTRON FLUX
Nuclear Criticality Safety Program (NCSP)
REACTOR CORE
REACTORS
REFLECTORS
RODS
THERMAL UTILIZATION
THICKNESS
VARIATIONS
VOLUME
ZONES