Modeling gamma detectors in OpenMC: Validation of a newly implemented pulse-height tally

Gamma spectroscopy measurements can be simulated using a pulse-height tally functionality of Monte Carlo particle transport codes. Such a functionality must account for the complete simulation history of a particle’s energy deposited in a particular volume. OpenMC, an open-source application for neu...

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Published inProgress in nuclear energy (New series) Vol. 172; p. 105186
Main Authors Fichtlscherer, Christopher, Miah, Milon, Frieß, Friederike, Göttsche, Malte, Kütt, Moritz
Format Journal Article
LanguageEnglish
Published Elsevier Ltd 01.07.2024
Subjects
Code development
Code validation
Detector modeling
Monte carlo particle transport code
OpenMC
Pulse height tally
OpenMC
Pulse height tally
Code development
Monte carlo particle transport code
Detector modeling
Code validation
Online AccessGet full text
ISSN0149-1970
DOI10.1016/j.pnucene.2024.105186

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Abstract Gamma spectroscopy measurements can be simulated using a pulse-height tally functionality of Monte Carlo particle transport codes. Such a functionality must account for the complete simulation history of a particle’s energy deposited in a particular volume. OpenMC, an open-source application for neutron and photon particle transport which is widely used in the nuclear engineering community, previously lacked adequate simulation capabilities for gamma spectroscopy. In this paper, we outline the implementation of the photon pulse-height tally for OpenMC. Additionally, we validate the new function by comparing results to analytical calculations, other software, and experimental data.
AbstractList Gamma spectroscopy measurements can be simulated using a pulse-height tally functionality of Monte Carlo particle transport codes. Such a functionality must account for the complete simulation history of a particle’s energy deposited in a particular volume. OpenMC, an open-source application for neutron and photon particle transport which is widely used in the nuclear engineering community, previously lacked adequate simulation capabilities for gamma spectroscopy. In this paper, we outline the implementation of the photon pulse-height tally for OpenMC. Additionally, we validate the new function by comparing results to analytical calculations, other software, and experimental data.
ArticleNumber 105186
Author Kütt, Moritz
Fichtlscherer, Christopher
Miah, Milon
Frieß, Friederike
Göttsche, Malte
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Keywords OpenMC
Pulse height tally
Code development
Monte carlo particle transport code
Detector modeling
Code validation
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Snippet Gamma spectroscopy measurements can be simulated using a pulse-height tally functionality of Monte Carlo particle transport codes. Such a functionality must...
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elsevier
SourceType Index Database
Publisher
StartPage 105186
SubjectTerms Code development
Code validation
Detector modeling
Monte carlo particle transport code
OpenMC
Pulse height tally
Title Modeling gamma detectors in OpenMC: Validation of a newly implemented pulse-height tally
URI https://dx.doi.org/10.1016/j.pnucene.2024.105186
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