Abstract

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)

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