Neutron Emission Characteristics of Two Mixed-Oxide Fuels: Simulations and Initial Experiments

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Simulations and experiments have been carried out to investigate the neutron emission characteristics of two mixed-oxide (MOX) fuels at Idaho National Laboratory (INL). These activities are part of a project studying advanced instrumentation techniques in support of the U.S. Department of Energy's Fuel Cycle Research and Development program and it's Materials Protection, Accounting, and Control for Transmutation (MPACT) campaign. This analysis used the MCNP-PoliMi Monte Carlo simulation tool to determine the relative strength and energy spectra of the different neutron source terms within these fuels, and then used this data to simulate the detection and measurement of these emissions using ... continued below

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Chichester, D. L.; Pozzi, S. A.; Dolan, J. L.; Flaska, M.; Johnson, J. T.; Seabury, E. H. et al. July 1, 2009.

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Simulations and experiments have been carried out to investigate the neutron emission characteristics of two mixed-oxide (MOX) fuels at Idaho National Laboratory (INL). These activities are part of a project studying advanced instrumentation techniques in support of the U.S. Department of Energy's Fuel Cycle Research and Development program and it's Materials Protection, Accounting, and Control for Transmutation (MPACT) campaign. This analysis used the MCNP-PoliMi Monte Carlo simulation tool to determine the relative strength and energy spectra of the different neutron source terms within these fuels, and then used this data to simulate the detection and measurement of these emissions using an array of liquid scintillator neutron spectrometers. These calculations accounted for neutrons generated from the spontaneous fission of the actinides in the MOX fuel as well as neutrons created via (alpha,n) reactions with oxygen in the MOX fuel. The analysis was carried out to allow for characterization of both neutron energy as well as neutron coincidences between multiple detectors. Coincidences between prompt gamma rays and neutrons were also analyzed. Experiments were performed at INL with the same materials used in the simulations to benchmark and begin validation tests of the simulations. Data was collected in these experiments using an array of four liquid scintillators and a high-speed waveform digitizer. Advanced digital pulse-shape discrimination algorithms were developed and used to collect this data. Results of the simulation and modeling studies are presented together with preliminary results from the experimental campaign.

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  • Report No.: INL/EXT-09-16566
  • Grant Number: DE-AC07-05ID14517
  • DOI: 10.2172/968682 | External Link
  • Office of Scientific & Technical Information Report Number: 968682
  • Archival Resource Key: ark:/67531/metadc926420

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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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  • July 1, 2009

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  • Nov. 13, 2016, 7:26 p.m.

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  • Jan. 4, 2017, 2:22 p.m.

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Chichester, D. L.; Pozzi, S. A.; Dolan, J. L.; Flaska, M.; Johnson, J. T.; Seabury, E. H. et al. Neutron Emission Characteristics of Two Mixed-Oxide Fuels: Simulations and Initial Experiments, report, July 1, 2009; [Idaho]. (digital.library.unt.edu/ark:/67531/metadc926420/: accessed April 23, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.