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In the 1970s at the Battelle Pacific Northwest Laboratory (PNL), a series of critical experiments using a remotely operated Split-Table Machine was performed with homogeneous mixtures of (Pu-U)O{sub 2}-polystyrene fuels in the form of square compacts having different heights. With respect to Pu enrichments and moderation [H/(Pu+U) atomic] ratios (MR), four-different homogeneous (Pu-U)O{sub 2}-polystyrene mixtures were considered: (Mixture 1) 7.6 wt% Pu with 19.5 MR, (Mixture 2) 7.89 wt% Pu with 51.8 MR, (Mixture 3) 14.62 wt% Pu with 30.6 MR, and (Mixture 4) 30.0 wt% Pu with 47.4 MR. The Pu{sup 240} isotopic contents in Pu were 23 wt% for Mixture 1 and 8 wt% for Mixtures 2-4. In all mixtures, the uranium was depleted to about 0.151 wt% U{sup 235}. The critical geometric dimensions for both fully Plexiglas{trademark} reflected and unreflected configurations were reported for Mixture 3 and 4 experiments. The dimensions for Mixture 1 and 2 experiments were given for fully-reflected assemblies. This evaluation contains a total of 39 critical (fully reflected and bare) experimental configurations as well as 3 slab geometry critical dimensions

osti oai (u.s. department of energy office of scientific and technical information)

Neutronics Benchmarks for the Utilization of Mixed-Oxide Fuel: Joint U.S./Russian Progress Report for Fiscal Year 1997, Volume 4, Part 7 - Homogeneous Mixtures of Polystyrene-Moderated Plutonium and Uranium Oxides