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- 저자 : P. Aguilera (검색결과 2 건)
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Calculation of kinetic parameters Beff and with modified open source Monte Carlo code OpenMC(TD)
J. Romero-Barrientos,J.I. Marquez Dami an,F. Molina,M. Zambra,P. Aguilera,F. Lopez-Usquiano,B. Parra,A. Ruiz 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.3
This work presents the methodology used to expand the capabilities of the Monte Carlo code OpenMC forthe calculation of reactor kinetic parameters: effective delayed neutron fraction beff and neutron generationtime L. The modified code, OpenMC(Time-Dependent) or OpenMC(TD), was then used tocalculate the effective delayed neutron fraction by using the prompt method, while the neutron generationtime was estimated using the pulsed method, fitting L to the decay of the neutron population. OpenMC(TD) is intended to serve as an alternative for the estimation of kinetic parameters whenlicensed codes are not available. The results obtained are compared to experimental data and MCNPcalculated values for 18 benchmark configurations.
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Romero-Barrientos J.,Molina F.,Márquez Damián J.I.,Zambra M.,Aguilera P.,López-Usquiano F.,Parra S. 한국원자력학회 2023 Nuclear Engineering and Technology Vol.55 No.5
In deterministic and Monte Carlo transport codes, b-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 b-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 e named Time Dependent OpenMC or OpenMC(TD)e time dependency related to b-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
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