Development of transient Monte Carlo in a fissile system with β-delayed emission from individual precursors using modified open source code OpenMC(TD)
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Fecha
2023-05
Profesor/a Guía
Facultad/escuela
Idioma
en
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Editor
Korean Nuclear Society
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Licencia CC
CC BY-NC-ND 4.0 Attribution-NonCommercial-NoDerivatives 4.0 International Deed
Licencia CC
https://creativecommons.org/licenses/by-nc-nd/4.0/
Resumen
In deterministic and Monte Carlo transport codes, β-delayed emission is included using a group structure where all of the precursors are grouped together in 6 groups or families, but given the increase in computational power, nowadays there is no reason to keep this structure. Furthermore, there have been recent efforts to compile and evaluate all the available β-delayed neutron emission data and to measure new and improved data on individual precursors. In order to be able to perform a transient Monte Carlo simulation, data from individual precursors needs to be implemented in a transport code. This work is the first step towards the development of a tool to explore the effect of individual precursors in a fissile system. In concrete, individual precursor data is included by expanding the capabilities of the open source Monte Carlo code OpenMC. In the modified code – named Time Dependent OpenMC or OpenMC(TD)– time dependency related to β-delayed neutron emission was handled by using forced decay of precursors and combing of the particle population. The data for continuous energy neutron cross-sections was taken from JEFF-3.1.1 library. Regarding the data needed to include the individual precursors, cumulative yields were taken from JEFF-3.1.1 and delayed neutron emission probabilities and delayed neutron spectra were taken from ENDF-B/VIII.0. OpenMC(TD) was tested in a monoenergetic system, an energy dependent unmoderated system where the precursors were taken individually or in a group structure, and in a light-water moderated energy dependent system, using 6-groups, 50 and 40 individual precursors. Neutron flux as a function of time was obtained for each of the systems studied. These results show the potential of OpenMC(TD) as a tool to study the impact of individual precursor data on fissile systems, thus motivating further research to simulate more complex fissile systems. © 2023 Korean Nuclear Society
Notas
Indexación: Scopus
Palabras clave
Individual Precursors, Monte Carlo, Open Source, OpenMC, Transient Monte Carlo
Citación
Nuclear Engineering and Technology. Volume 55, Issue 5, Pages 1593 - 1603. May 2023
DOI
10.1016/j.net.2023.02.006