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

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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% ... continued below

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15 p.

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Yavuz, M. May 1, 1999.

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Description

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.

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15 p.

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INIS; OSTI as DE00007207

Medium: P; Size: 15 pages

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  • Other Information: PBD: 1 May 1999

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  • Report No.: ORNL/SUB/99-XSZ175V-2
  • Grant Number: AC05-96OR22464
  • DOI: 10.2172/7207 | External Link
  • Office of Scientific & Technical Information Report Number: 7207
  • Archival Resource Key: ark:/67531/metadc711775

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  • May 1, 1999

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  • Sept. 12, 2015, 6:31 a.m.

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  • April 7, 2017, 3:04 p.m.

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Yavuz, M. 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, report, May 1, 1999; Tennessee. (digital.library.unt.edu/ark:/67531/metadc711775/: accessed November 18, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.