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Title:Advanced Monte Carlo analysis of ex-vessel neutron dosimetry for cycle 25 of Krško nuclear power plant
Authors:ID Goričanec, Tanja, Institut "Jožef Stefan" (Author)
ID Barbarič, Benjamin, Institut "Jožef Stefan" (Author)
ID Radulović, Vladimir, Institut "Jožef Stefan" (Author)
ID Čalič, Dušan, Institut "Jožef Stefan" (Author)
ID Snoj, Luka, Institut "Jožef Stefan" (Author)
ID Kromar, Marjan, Institut "Jožef Stefan" (Author)
Files:URL URL - Source URL, visit https://www.sciencedirect.com/science/article/pii/S1738573325004553
 
.pdf PDF - Presentation file, download (19,81 MB)
MD5: 0553556B14412D9ADC3DCA27B84166A6
Description: Raziskovalni podatki so na voljo na povezavi: https://zenodo.org/records/14887749.
 
Language:English
Typology:1.01 - Original Scientific Article
Organization:Logo IJS - Jožef Stefan Institute
Abstract:This paper presents the results of Monte Carlo neutron transport calculations performed for the containment building of the Krško Nuclear Power Plant. The calculations were performed using the Monte Carlo N-Particle Transport Code (MCNP) in combination with the ADVANTG hybrid code to speed up the convergence of the results outside the reactor core. The paper focuses on the analysis of the Ex-Vessel Neutron Dosimetry (EVND) program conducted during the 25th fuel cycle at the Krško nuclear power plant with the irradiation of gradient chains and multiple foil sensor sets. The calculated reaction rates at the dosimeter locations are in good agreement with the measured values. However, deviations were observed in the thermal part of the neutron energy spectrum which cannot be neglected, and investigated were some possible reasons for the deviations: nuclear data, concrete material composition, concrete geometry, sensor position and impurities in sample.
Keywords:neutron transport, ex-vessel neutron dosimeters, neutron
Publication status:Published
Publication version:Version of Record
Submitted for review:16.06.2025
Article acceptance date:26.08.2025
Publication date:01.09.2025
Publisher:Elsevier
Year of publishing:2026
Number of pages:str. 1-37
Numbering:Vol. 58, iss. 1, [article no.] 103887
Source:Južna Koreja
PID:20.500.12556/DiRROS-23891 New window
UDC:539.1
ISSN on article:2234-358X
DOI:10.1016/j.net.2025.103887 New window
COBISS.SI-ID:253273091 New window
Copyright:© 2025 Korean Nuclear Society, Published by Elsevier Korea LLC
Note:Nasl. z nasl. zaslona; Soavtorji: Benjamin Barbarič, Vladimir Radulović, Dušan Čalič, Luka Snoj, Marjan Kromar; Opis vira z dne 15. 10. 2025;
Publication date in DiRROS:20.10.2025
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Downloads:74
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Record is a part of a journal

Title:Nuclear engineering and technology
Shortened title:Nucl. eng. technol
Publisher:Korean Nuclear Society
ISSN:2234-358X
COBISS.SI-ID:248769027 New window

Document is financed by a project

Funder:Slovenian Nuclear Safety Administration
Project number:C2563-24-430012
Name:Izračun transporta nevtronov v zadrževalnem hramu jedrske elektrarne Krško z uporabo Monte Carlo metode

Funder:ARIS - Slovenian Research and Innovation Agency
Project number:V2-2531
Name:Napredne računske simulacije za analizo nevtronskih poškodb reaktorske posode tlačnovodne jedrske elektrarne

Licences

License:CC BY-NC-ND 4.0, Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 International
Link:http://creativecommons.org/licenses/by-nc-nd/4.0/
Description:The most restrictive Creative Commons license. This only allows people to download and share the work for no commercial gain and for no other purposes.
Licensing start date:01.09.2025
Applies to:VoR

Secondary language

Language:Slovenian
Keywords:transport nevtronov, dozimetri


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