Feasibility of fissile mass assay of spent nuclear fuel using {sup 252}Cf-source-driven frequency-analysis

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The feasibility was evaluated using MCNP-DSP, an analog Monte Carlo transport cod to simulate source-driven measurements. Models of an isolated Westinghouse 17x17 PWR fuel assembly in a 1500-ppM borated water storage pool were used. In the models, the fuel burnup profile was represented using seven axial burnup zones, each with isotopics estimated by the PDQ code. Four different fuel assemblies with average burnups from fresh to 32 GWd/MTU were modeled and analyzed. Analysis of the fuel assemblies was simulated by inducing fission in the fuel using a {sup 252}Cf source adjacent to the assembly and correlating source fissions with the ... continued below

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8 p.

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Mattingly, J. K.; Valentine, T. E. & Mihalczo, J. T. October 1996.

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The feasibility was evaluated using MCNP-DSP, an analog Monte Carlo transport cod to simulate source-driven measurements. Models of an isolated Westinghouse 17x17 PWR fuel assembly in a 1500-ppM borated water storage pool were used. In the models, the fuel burnup profile was represented using seven axial burnup zones, each with isotopics estimated by the PDQ code. Four different fuel assemblies with average burnups from fresh to 32 GWd/MTU were modeled and analyzed. Analysis of the fuel assemblies was simulated by inducing fission in the fuel using a {sup 252}Cf source adjacent to the assembly and correlating source fissions with the response of a bank of {sup 3}He detectors adjacent to the assembly opposite the source. This analysis was performed at 7 different axial positions on each of the 4 assemblies, and the source-detector cross-spectrum signature was calculated for each of these 28 simulated measurements. The magnitude of the cross-spectrum signature follows a smooth upward trend with increasing fissile material ({sup 235}U and {sup 239}Pu) content, and the signature is independent of the concentration of spontaneously fissioning isotopes (e.g., {sup 244}Cm) and ({alpha},n) sources. Furthermore, the cross-spectrum signature is highly sensitive to changes in fissile material content. This feasibility study indicated that the signature would increase {similar_to}100% in response to an increase of only 0.1 g/cm{sup 3} of fissile material.

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8 p.

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INIS; OSTI as DE96015231

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  • 37. annual meeting of the Institute of Nuclear Materials Management, Naples, FL (United States), 28 Jul - 1 Aug 1996

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  • Other: DE96015231
  • Report No.: CONF-960767--70
  • Grant Number: AC05-96OR22464
  • Office of Scientific & Technical Information Report Number: 391688
  • Archival Resource Key: ark:/67531/metadc679687

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  • October 1996

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  • July 25, 2015, 2:20 a.m.

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  • Oct. 3, 2017, 1:06 p.m.

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Mattingly, J. K.; Valentine, T. E. & Mihalczo, J. T. Feasibility of fissile mass assay of spent nuclear fuel using {sup 252}Cf-source-driven frequency-analysis, article, October 1996; Tennessee. (digital.library.unt.edu/ark:/67531/metadc679687/: accessed October 21, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.