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Research Articles

Benchmarking Neutron Counting System for Passive Measurements and Active Interrogation of Unknown Objects for Fissile and Fissionable Materials Determination

, ORCID Icon, ORCID Icon & ORCID Icon
Pages 1252-1267 | Received 01 Dec 2021, Accepted 07 Apr 2023, Published online: 23 May 2023

References

  • N. ENSSLIN, “Chapter 11: The Origin of Neutron Radiation,” Passive Nondestructive Assay of Nuclear Materials, pp. 337–356, D. REILLY, N. ENSSLIN, and H. SMITH JR., Eds., Office of Nuclear Regulatory Research, U. S. Nuclear Regulatory Commission (1991).
  • R. C. RUNKLE, D. L. CHICHESTER, and S. J. THOMPSON, “Rattling Nucleons: New Developments in Active Interrogation of Special Nuclear Material,” Nucl. Instrum. Methods Phys. Res. A, 663, 75 (2012); https://doi.org/10.1016/j.nima.2011.09.052.
  • S. AMIEL, “Analytical Applications of Delayed Neutron Emission in Fissionable Elements,” Anal. Chem., 34, 13, 1683 (1962); https://doi.org/10.1021/ac60193a010.
  • “Official Gazette of the United States Patent Office Volume 903 Issues 3–5,” United States Patent and Trademark Office (1972).
  • “Nuclear Safeguards Research and Development Program Status Report May-August 1971,” LA-4794-MS, Los Alamos Scientific Laboratory (1971).
  • A. L. LOUSTEAU et al., “Determining 235U Enrichment in Bulk Uranium Items Using Dual-Energy Interrogation with Delayed Neutron Measurement,” Nucl. Instrum. Methods Phys. Res. A, 904, 74 (2018); https://doi.org/10.1016/j.nima.2018.07.030.
  • P. M. RINARD, “Application Guide to Shufflers,” LA-13819-MS, Los Alamos National Laboratory (2001).
  • R. D. MCELROY JR. and S. L. CLEVELAND, “The D-D Neutron Generator as an Alternative to Am(Li) Isotopic Neutron Source in the Active Well Coincidence Counter,” ORNL/TM-2017/57, Oak Ridge National Laboratory (2017).
  • “Standard Test Method for Nondestructive Assay of Nuclear Material in Scrap and Waste by Passive-Active Neutron Counting Using 252Cf Shuffler,” ASTM C1316, American Society for Testing and Materials (2008).
  • R. B. ROGGE et al., “Non-destructive Examination Using Neutrons: A Nuclear Waste and Orphaned Source Characterization Case Study Applicable to Nuclear Forensics,” AECL Nucl. Rev., 4, 2, 141 (2015); https://doi.org/10.12943/CNR.2015.00051.
  • C. J. WERNER, “MCNP6® User’s Manual Code Version 6.2,” LANL Report LA-UR-17-29981 Rev. 0, Los Alamos National Laboratory (2017).
  • G. BENTOUMI et al., “A Novel In-Beam Delayed Neutron Counting Technique for Characterization of Special Nuclear Materials,” IEEE Trans. Nucl. Sci., 63, 6, 2807 (2016); https://doi.org/10.1109/TNS.2016.2624146.
  • “SK02197-01 Cylindrical He3 Neutron Detector,” LND, Inc. (2015).
  • M. BRUGGEMAN et al., “Neutron Coincidence Counting Based on Time Interval Analysis with One- and Two-Dimensional Rossi-Alpha Distributions: An Application for Passive Neutron Waste Assay,” Nucl. Instrum. Methods Phys. Res., Sect. A, 382, 3, 511 (1996); https://doi.org/10.1016/S0168-9002(96)00795-4.
  • “GBS Elektronik Home Page,” GBS Elektronik GmbH (2018); https://www.gbs-elektronik.de/en/home.php?lang=EN ( accessed Dec. 2018).
  • “Radiation Monitoring: Survey Meters, Monitors and Counters,” Bot Engineering Limited (2016); http://www.botengineering.com/radiationmonitoring.html ( accessed June 2019).
  • J. ATANACKOVIC et al., “Characterization of Neutron Fields from Bare and Heavy Water Moderated 252Cf Spontaneous Fission Source Using Bonner Sphere Spectrometer,” Appl. Radiat. Isot., 99, 122 (2015); https://doi.org/10.1016/j.apradiso.2015.02.023.
  • J. K. SHULTIS and R. E. FAW, “An MCNP Primer,” (2011); Kansas State University, Department of Mechanical and Nuclear Engineering (2004); https://www.mne.k-state.edu/~jks/MCNPprmr.pdf ( accessed Feb. 2019).
  • “Evaluated Nuclear Data File (ENDF) Database,” International Atomic Energy Agency (2017); https://www-nds.iaea.org/exfor/endf.htm ( accessed Jan. 2017).
  • “PENDL: Plotter for Evaluated Nuclear Data Libraries,” Japan Charged-Particle Nuclear Reaction Data Group (2014); https://www.jcprg.org/endf/ ( accessed Dec. 2018).
  • F. ALI and G. BENTOUMI, “MCNP6 Simulations of Active Neutron Interrogation of Fissile Samples Using a Deuterium-Deuterium Neutron Generator,” presented at the 13th Int. Topl. Mtg. on the Nuclear Applications of Accelerators, Quebec City, Quebec, August 2017.
  • D. B. PELOWITZ, “MCNP6TM User’s Manual Version 1.0,” LANL Report LA-CP-13-00634 Rev. 0, Los Alamos National Laboratory (2013).

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