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...

Full description

Saved in:
Bibliographic Details
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

Cover

More Information
Summary: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.
ISSN:0149-1970
DOI:10.1016/j.pnucene.2024.105186