For radiological neutron surveying, neutron detectors require shielding to minimize contributions from sources outside the area of interest. To test the effectiveness of such a shield, Monte Carlo N-Particle Transport Codes (MCNP) were used to model a neutron detector so that the effectiveness of such a shield design could be explored. In this research, MCNP models of a ¹⁰B/ZnS detector within a shield were developed and compared to experimental results. By carefully modeling the specifics of the neutron detector as well as the neutron source used in the experiments, the simulation was able to accurately predict the experimental results within 20%.

1. Neutron Detector Suitable for Second Line of Defense Program, Bridgeport Instruments LLC, Austin, TX, USA, 2020.
   Retrieved from: http://bridgeportinstruments.com/products/neutron/ndet_2x24_r1.pdf
   Retrieved on: August 20, 2021.
2. P. A. Söderström et al., “Characterization of a Plutonium-Beryllium Neutron Source,” Applied Radiation and Isotopes, vol. 167, article no. 109441, Jan. 2021.
   DOI: https://doi.org/10.1016/j.apradiso.2020.109441
   PMid: 33002762
3. S. F. Mughabghab, Thermal Neutron Capture Cross Sections Resonance Integrals and G-Factors , Rep. INDC(NDS)-440, IAEA, Vienna, Austria, 2003.
   Retrieved from: https://inis.iaea.org/collection/NCLCollectionStore/_Public/34/020/34020739.pdf?r=1
   Retrieved on: Sep. 17, 2021
4. K. Guzman-Garcia et al., “10B+ZnS(Ag) as an Alternative to 3He-Based Detectors for Radiation Portal Monitors,” EPJ Web of Conferences, vol. 153, article no. 07008, 2017.
   DOI: https://doi.org/10.1051/epjconf/201715307008
5. Atlas of Neutron Capture Cross Sections , Evaluated Data Library, IAEA, Vienna, Austria, 2010.
   Retrieved from: https://www.iaea.org/resources/databases/atlas-of-neutron-capture-cross-sections
   Retrieved on: August 20, 2021
6. Compendium of Material Composition Data for Radiation Transport Modeling , Rep. 200-DMAMC-128170 PNNL-15870, Rev. 2, Pacific Northwest National Laboratory, Richland, WA, USA, Apr. 2021.
   Retrieved from: https://www.pnnl.gov/main/publications/external/technical_reports/PNNL-15870Rev2.pdf
   Retrieved on: August 20, 2021
7. W.B. Wilson et al., SOURCES 4A: A Code for Calculating (α, n), Spontaneous Fission, and Delayed Neutron sources and Spectra , Rep. LA-13639-MS, Los Alamos National Laboratory, Los Alamos, New Mexico, USA, 1999.
   DOI: https://doi.org/10.2172/15215
8. J. K. Shultis., R. E. Faw, An MCNP Primer, Kansas State University, Manhattan, KS, USA, 2011.
   Retrieved from: https://www.mne.k-state.edu/~jks/MCNPprmr.pdf
   Retrieved on: August 20, 2021
9. M.S. Dewey, H.P. Mumm, “Calibrations: Neutron Source Strength,” National Institute of Standards and Technology, U.S. Department of Commerce, Gaithersburg, MD, USA 2010.
   Retrieved from: https://www.nist.gov/programs-projects/calibrations-neutron-source-strength
   Retrieved on: November 18, 2021
10. H.R. Vega-Carrillo et al. “Characterization of a ²³⁹PuBe Isotopic Neutron Source,” in Proceedings of the ISSSD, IAEA, Vienna, Austria, 2012.
    Retrieved from: https://inis.iaea.org/collection/NCLCollectionStore/_Public/44/026/44026243.pdf
    Retrieved on: November 18, 2021

Alexander Macris, Kevin McKay, William Charlton, Cheryl Brabec, Sheldon Landsberger, "Development of an mcnp model of a boron-10 zinc sulfide silver-activated [¹⁰B/ZnS(Ag)] detector and directional shielding using radiation counting", RAD Conf. Proc, vol. 5, 2021, pp. 104–109, http://doi.org/10.21175/RadProc.2021.20