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Nuclear Technology Volume 209, 2023 - Issue 9
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Research Articles

An Experimental Validation of Spectrally Matched Neutron Detection Systems Using 3He and BF3

Codey OlsonUniversity of Utah Nuclear Engineering Program, Department of Civil and Environmental Engineering, 110 Central Campus Drive, Suite 2000, Salt Lake City, Utah84112Correspondence[email protected]
ORCID Iconhttps://orcid.org/0000-0001-9646-9783View further author information
ORCID Icon,
Jesse SnowUniversity of Utah Nuclear Engineering Program, Department of Civil and Environmental Engineering, 110 Central Campus Drive, Suite 2000, Salt Lake City, Utah84112View further author information
,
Meng-Jen (Vince) WangUniversity of Utah Nuclear Engineering Program, Department of Civil and Environmental Engineering, 110 Central Campus Drive, Suite 2000, Salt Lake City, Utah84112View further author information
,
Glenn SjodenUniversity of Utah Nuclear Engineering Program, Department of Civil and Environmental Engineering, 110 Central Campus Drive, Suite 2000, Salt Lake City, Utah84112View further author information
&
Edward CazalasUniversity of Utah Nuclear Engineering Program, Department of Civil and Environmental Engineering, 110 Central Campus Drive, Suite 2000, Salt Lake City, Utah84112View further author information
Pages 1241-1251 | Received 13 Jan 2023, Accepted 11 Apr 2023, Published online: 22 May 2023

References

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  • S. WALKER, “Spectrally-Matched Neutron Detectors Designed Using Computational Adjoint Sn for Plug-In Replacement of 3He,” PhD Thesis, Georgia Institute of Technology (2013).
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  • W. A. WIESELQUIST, R. A. LEFEBVRE, and M. A. JESSEE, “SCALE Code System,” NL/Tm-2005/39April, Oak Ridge National Laboratory (2020).
  • G. GHITA, G. SJODEN, and J. BACIAK, “A Methodology for Experimental and 3-D Computational Radiation Transport Assessment of Pu-Be Neutron Sources,” Nucl. Technol., 159, 3, 319 (2007); https://doi.org/10.13182/NT07-A3879.
  • M. J. WANG and G. E. SJODEN, “Experimental and Computational Dose Rate Evaluation Using SN and Monte Carlo Method for a Packaged 241AmBe Neutron Source,” Nucl. Sci. Eng., 195, 11, 1154 (2021); https://doi.org/10.1080/00295639.2021.1906587.

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