Gamma-Ray Simulated Spectrum Deconvolution of a LaBr₃ 1-in. x 1-in. Scintillator for Nondestructive ATR Fuel Burnup On-Site Predictions

Navarro, Jorge; Ring, Terry A.; Nigg, David W.

doi:10.13182/NT14-4

Title: Gamma-Ray Simulated Spectrum Deconvolution of a LaBr₃ 1-in. x 1-in. Scintillator for Nondestructive ATR Fuel Burnup On-Site Predictions

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Abstract

A deconvolution method for a LaBr₃ 1"x1" detector for nondestructive Advanced Test Reactor (ATR) fuel burnup applications was developed. The method consisted of obtaining the detector response function, applying a deconvolution algorithm to 1”x1” LaBr₃ simulated, data along with evaluating the effects that deconvolution have on nondestructively determining ATR fuel burnup. The simulated response function of the detector was obtained using MCNPX as well with experimental data. The Maximum-Likelihood Expectation Maximization (MLEM) deconvolution algorithm was selected to enhance one-isotope source-simulated and fuel- simulated spectra. The final evaluation of the study consisted of measuring the performance of the fuel burnup calibration curve for the convoluted and deconvoluted cases. The methodology was developed in order to help design a reliable, high resolution, rugged and robust detection system for the ATR fuel canal capable of collecting high performance data for model validation, along with a system that can calculate burnup and using experimental scintillator detector data.

Authors:

Navarro, Jorge ^[1]; Ring, Terry A. ^[2]; Nigg, David W. ^[3]

Idaho National Lab. (INL), Idaho Falls, ID (United States). Center for Space Nuclear Research
Univ. of Utah, Salt Lake City, UT (United States). Dept. of Chemical Engineering, Utah Nuclear Engineering Program
Idaho National Lab. (INL), Idaho Falls, ID (United States). Reactor Physics Analysis and Design

Publication Date:: Sun Mar 01 00:00:00 EST 2015

Research Org.:: Idaho National Lab. (INL), Idaho Falls, ID (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 1178058

Report Number(s):: INL/JOU-13-30955
Journal ID: ISSN 0029-5450

Grant/Contract Number:: AC07-05ID14517

Resource Type:: Accepted Manuscript

Journal Name:: Nuclear Technology

Additional Journal Information:: Journal Volume: 190; Journal Issue: 2; Journal ID: ISSN 0029-5450

Publisher:: American Nuclear Society (ANS)

Country of Publication:: United States

Language:: English

Subject:: 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; Deconvolution, LaBr3, High-Enriched Fuel Burnup Predictions; Advanced Test Reactor (ATR)

Citation Formats


                    Navarro, Jorge, Ring, Terry A., and Nigg, David W. Gamma-Ray Simulated Spectrum Deconvolution of a LaBr₃ 1-in. x 1-in. Scintillator for Nondestructive ATR Fuel Burnup On-Site Predictions.  United States: N. p., 2015. 
Web.  doi:10.13182/NT14-4.

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                    Navarro, Jorge, Ring, Terry A., & Nigg, David W. Gamma-Ray Simulated Spectrum Deconvolution of a LaBr₃ 1-in. x 1-in. Scintillator for Nondestructive ATR Fuel Burnup On-Site Predictions.  United States.  https://doi.org/10.13182/NT14-4

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                    Navarro, Jorge, Ring, Terry A., and Nigg, David W. Sun .  
"Gamma-Ray Simulated Spectrum Deconvolution of a LaBr₃ 1-in. x 1-in. Scintillator for Nondestructive ATR Fuel Burnup On-Site Predictions".  United States.  https://doi.org/10.13182/NT14-4.  https://www.osti.gov/servlets/purl/1178058.

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@article{osti_1178058,

  title        = {Gamma-Ray Simulated Spectrum Deconvolution of a LaBr₃ 1-in. x 1-in. Scintillator for Nondestructive ATR Fuel Burnup On-Site Predictions},

  author       = {Navarro, Jorge and Ring, Terry A. and Nigg, David W.},

  abstractNote = {A deconvolution method for a LaBr₃ 1"x1" detector for nondestructive Advanced Test Reactor (ATR) fuel burnup applications was developed. The method consisted of obtaining the detector response function, applying a deconvolution algorithm to 1”x1” LaBr₃ simulated, data along with evaluating the effects that deconvolution have on nondestructively determining ATR fuel burnup. The simulated response function of the detector was obtained using MCNPX as well with experimental data. The Maximum-Likelihood Expectation Maximization (MLEM) deconvolution algorithm was selected to enhance one-isotope source-simulated and fuel- simulated spectra. The final evaluation of the study consisted of measuring the performance of the fuel burnup calibration curve for the convoluted and deconvoluted cases. The methodology was developed in order to help design a reliable, high resolution, rugged and robust detection system for the ATR fuel canal capable of collecting high performance data for model validation, along with a system that can calculate burnup and using experimental scintillator detector data.},

  doi          = {10.13182/NT14-4},

  journal      = {Nuclear Technology},

  number       = 2,

  volume       = 190,

  place        = {United States},

  year         = {Sun Mar 01 00:00:00 EST 2015},

  month        = {Sun Mar 01 00:00:00 EST 2015}

}

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