Evaluation of plutonium oxidation using pulsed neutron measurements with {sup 252}Cf

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The unrecognized oxidation of plutonium in {open_quotes}sealed{close_quotes} canisters poses a unique problem for both material control and accountability. A feasibility study was performed to address the use of randomly pulsed neutron measurements with {sup 252}Cf to determine if plutonium metal in a canister has oxidized without opening the container. The Monte Carlo code MCNP-DSP was used to determine if time-of-flight transmission measurements could be used to determine oxidation of plutonium in {open_quotes}sealed{close_quotes} cans. In the Monte Carlo models, a plutonium button in a can was positioned between a {sup 252}Cf source and a scintillation detector, and the time distribution of ... continued below

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7 p.

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Valentine, T.E. & Mihalczo, J.T. September 1, 1997.

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Description

The unrecognized oxidation of plutonium in {open_quotes}sealed{close_quotes} canisters poses a unique problem for both material control and accountability. A feasibility study was performed to address the use of randomly pulsed neutron measurements with {sup 252}Cf to determine if plutonium metal in a canister has oxidized without opening the container. The Monte Carlo code MCNP-DSP was used to determine if time-of-flight transmission measurements could be used to determine oxidation of plutonium in {open_quotes}sealed{close_quotes} cans. In the Monte Carlo models, a plutonium button in a can was positioned between a {sup 252}Cf source and a scintillation detector, and the time distribution of counts after {sup 252}Cf fission in the detector was calculated. The time distribution of counts after {sup 252}Cf fission differs between plutonium metal and plutonium oxide because resonances in oxygen will affect transmission of certain energy neutrons from {sup 252}Cf sources in ionization chambers. This method could be used to determine the presence of other materials that react with plutonium in {open_quotes}sealed{close_quotes} cans.

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7 p.

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INIS; OSTI as DE97008476

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  • 38. annual meeting of the Institute of Nuclear Materials management, Phoenix, AZ (United States), 20-24 Jul 1997

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  • Other: DE97008476
  • Report No.: CONF-970744--22
  • Grant Number: AC05-96OR22464
  • Office of Scientific & Technical Information Report Number: 522712
  • Archival Resource Key: ark:/67531/metadc692977

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • September 1, 1997

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  • Aug. 14, 2015, 8:43 a.m.

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  • Jan. 25, 2016, 12:49 p.m.

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Valentine, T.E. & Mihalczo, J.T. Evaluation of plutonium oxidation using pulsed neutron measurements with {sup 252}Cf, article, September 1, 1997; Tennessee. (digital.library.unt.edu/ark:/67531/metadc692977/: accessed October 16, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.