Measurement and Characterization of Nuclear Material at Idaho National Laboratory

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A measurement plan and preliminary Monte Carlo simulations are presented for the investigation of well-defined mixed-oxide fuel pins. Measurement analysis including pulse-height distributions and time-dependent cross-correlation functions will be performed separately for neutrons and gamma rays. The utilization of Monte Carlo particle transport codes, specifically MCNP-PoliMi, is discussed in conjunction with the anticipated measurements. Four EJ-309 liquid scintillation detectors with an accurate pulse timing and digital, offline, optimized pulse-shape discrimination method will be used to prove the dependency of pulse-height distributions, cross-correlation functions, and material multiplicities upon fuel pin composition, fuel pin quantity, and detector geometry. The objective of the ... continued below

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Dolan, J. L.; Flaska, M.; Pozzi, S. A. & Chichester, D. L. July 1, 2009.

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A measurement plan and preliminary Monte Carlo simulations are presented for the investigation of well-defined mixed-oxide fuel pins. Measurement analysis including pulse-height distributions and time-dependent cross-correlation functions will be performed separately for neutrons and gamma rays. The utilization of Monte Carlo particle transport codes, specifically MCNP-PoliMi, is discussed in conjunction with the anticipated measurements. Four EJ-309 liquid scintillation detectors with an accurate pulse timing and digital, offline, optimized pulse-shape discrimination method will be used to prove the dependency of pulse-height distributions, cross-correlation functions, and material multiplicities upon fuel pin composition, fuel pin quantity, and detector geometry. The objective of the measurements and simulations is to identify novel methods for describing mixed-oxide fuel samples by relating measured quantities to fuel characteristics such as criticality, mass quantity, and material composition. This research has applications in nuclear safeguards and nonproliferation.

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  • INMM Annual Meeting,Tucson, Ariz,07/12/2009,07/16/2009

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  • Report No.: INL/CON-09-16103
  • Grant Number: DE-AC07-05ID14517
  • Office of Scientific & Technical Information Report Number: 968681
  • Archival Resource Key: ark:/67531/metadc926806

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  • July 1, 2009

Added to The UNT Digital Library

  • Nov. 13, 2016, 7:26 p.m.

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  • Jan. 4, 2017, 2:22 p.m.

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Dolan, J. L.; Flaska, M.; Pozzi, S. A. & Chichester, D. L. Measurement and Characterization of Nuclear Material at Idaho National Laboratory, article, July 1, 2009; [Idaho]. (digital.library.unt.edu/ark:/67531/metadc926806/: accessed October 21, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.