Issue |
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
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|
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Article Number | 04024 | |
Number of page(s) | 8 | |
Section | Monte Carlo Transport | |
DOI | https://doi.org/10.1051/epjconf/202124704024 | |
Published online | 22 February 2021 |
https://doi.org/10.1051/epjconf/202124704024
EFFECT OF THE UNIFORM FISSION SOURCE METHOD ON LOCAL POWER VARIANCE IN FULL CORE SERPENT CALCULATION
1 Helmholtz-Zentrum Dresden-Rossendorf Dresden, Germany
2 VTT Technical Centre of Finland, Ltd Espoo, Finland
y.bilodid@hzdr.de
Jaakko.Leppanen@vtt.fi
Published online: 22 February 2021
One of challenges of the Monte Carlo full core simulations is to obtain acceptable statistical variance of local parameters throughout the whole reactor core at a reasonable computation cost. The statistical variance tends to be larger in low-power regions. To tackle this problem, the Uniform-Fission-Site method was implemented in Monte Carlo code MC21 and its effectiveness was demonstrated on NEA Monte Carlo performance benchmark. The very similar method is also implemented in Monte Carlo code Serpent under the name Uniform Fission Source (UFS) method.
In this work the effect of UFS method implemented in Serpent is studied on the BEAVRS benchmark which is based on a real PWR core with relatively flat radial power distribution and also on 3x3 PWR mini-core simulated with thermo-hydraulic and thermo-mechanic feedbacks. It is shown that the application of the Uniform Fission Source method has no significant effect on radial power variance but equalizes axial distribution of variance of local power.
Key words: Serpent / Monte Carlo / Uniform Fission Source / variance reduction
© The Authors, published by EDP Sciences, 2021
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