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Extra resources for Nuclear criticality safety experiments, calculations, and analyses, 1958 to 1982 : compilation of papers from the Transactions of the American Nuclear Society
The buckling was obtained from the critical size of the assemblies and the extrapolation distance. 3 cm. 87 cm' The delayed-neutron age to thermal was calculated by 3. G. Sullivan using a Monte 'Carlo moments-method calculation. 6 cm'. 0048. 196. The results of the critical experiments a r e given in Table I. . 6 Average Critical Height (cm) Critical Mass (kg of . 30 x IO-' 'J. T. Mihalczo, "Determination of Infinite Medium Multiplication Factor for 2% Uranium-235 Enriched UFI in Paraffin," Trans.
The fuel elements were 5 ft. long. The subcrltlcal lattice was placed on the thermal column of a water boiler reactor which served as the source of neutrons for the assembly. ) of the graphite used was first measured. The thermal-neutron distributions along the vertical and the horizontal axes of this block were determined from the activations of sets of bare and cadmium-covered indium foils. 2 cm. 8 cm. obtained previously' for this block. The material buckling of the lattice was determined from the thermal-neutron flux distribution measured parallel to the vertical axis of the assembly.
J . Lynn (ORNL). A series of neutron multiplication measurements with arrays of 1 by 8 by 10 in. 4% U-235 enriched uranlum metal have been made to provide data from which safety criteria for the storage of these fissile units can be established. 9 kg of U-235. A maximum of 125 units was assembled. The arrays studied were cubic lattices of the units and were usually paralleleplpal in shape. -thick Plexiglas reflector. 06. 023 would require 250 i 30 units. In lattices In which the fissile units a r e separated by 1 in.