Statistical signal processing and artificial intelligence applications in the nondestructive assay of U/Pu bearing materials

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Over the years a number of techniques have been developed to determine the quantity and distribution of radiative isotopes contained in given assay samples through the measurement and analysis of penetrating characteristic radiations. An active technique of particular utility when assaying samples containing very small quantities of fissionable material or when high gamma ray backgrounds are encountered is the delayed neutron nondestructive assay (DN-NDA) technique. Typically, analysis of the delayed neutron signal involves relating the gross delayed neutron count observed following neutron irradiation of an assay sample to total fissionable material present via a linear calibration curve. In this way, ... continued below

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5 p.

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Aumeier, S.E. & Forsmann, J.H. October 1, 1997.

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  • Argonne National Laboratory
    Publisher Info: Argonne National Lab., Idaho Falls, ID (United States)
    Place of Publication: Idaho Falls, Idaho

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Description

Over the years a number of techniques have been developed to determine the quantity and distribution of radiative isotopes contained in given assay samples through the measurement and analysis of penetrating characteristic radiations. An active technique of particular utility when assaying samples containing very small quantities of fissionable material or when high gamma ray backgrounds are encountered is the delayed neutron nondestructive assay (DN-NDA) technique. Typically, analysis of the delayed neutron signal involves relating the gross delayed neutron count observed following neutron irradiation of an assay sample to total fissionable material present via a linear calibration curve. In this way, the technique is capable of yielding the mass of a single dominant fissionable isotope or the total fissionable mass contained in a sample. Using this approach the only way to determine the mass of individual fissionable isotopes contained in a sample is to correlate total fissionable mass to individual isotopics via calculations or other means, yielding an indirect measure of isotopics. However, there is isotope specific information in the temporal delayed neutron signal due to differences in the delayed neutron precursor yields resulting from the fissioning of different isotopes. The authors present the results of an analysis to evaluate the feasibility of using Kalman filters and genetic algorithms to determine multiple specific fissionable isotopic masses contained in an assay sample from a cumulative delayed neutron signal measured following neutron irradiation of the sample.

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5 p.

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INIS; OSTI as DE97008378

Source

  • Plutonium futures: the science, Santa Fe, NM (United States), 25-27 Aug 1997

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  • Other: DE97008378
  • Report No.: ANL/ED/CP--92749
  • Report No.: CONF-970844--6
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 537353
  • Archival Resource Key: ark:/67531/metadc694584

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Office of Scientific & Technical Information Technical Reports

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  • October 1, 1997

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  • Aug. 14, 2015, 8:43 a.m.

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  • May 16, 2016, 5:56 p.m.

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Aumeier, S.E. & Forsmann, J.H. Statistical signal processing and artificial intelligence applications in the nondestructive assay of U/Pu bearing materials, article, October 1, 1997; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc694584/: accessed December 15, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.