Development of transient Monte Carlo in a fissile system with i3 delayed emission from individual precursors using modified open source code OpenMC(TD)

Romero-Barrientos, J.; Molina, F.; Damian, J. I. Marquez; Zambra, M.; Aguilera, P.; Lopez-Usquiano, F.; Parra, S.

Abstract

In deterministic and Monte Carlo transport codes, i3-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 i3-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 i3-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, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).

Más información

Título según WOS: ID WOS:001028250600001 Not found in local WOS DB
Título de la Revista: NUCLEAR ENGINEERING AND TECHNOLOGY
Volumen: 55
Número: 5
Editorial: KOREAN NUCLEAR SOC
Fecha de publicación: 2023
Página de inicio: 1593
Página final: 1603
DOI:

10.1016/j.net.2023.02.006

Notas: ISI