Effect of the uniform fission source method on local power variance in full core serpent calculation

Yurii Bilodid; Jaakko Leppänen

doi:10.1051/epjconf/202124704024

Effect of the uniform fission source method on local power variance in full core serpent calculation

Yurii Bilodid, Jaakko Leppänen

Helmholtz Centre Dresden-Rossendorf (HZDR)

Research output: Contribution to journal › Article in a proceedings journal › Scientific › peer-review

Abstract

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.

Original language	English
Pages (from-to)	871-878
Number of pages	8
Journal	EPJ Web of Conferences
Volume	247
DOIs	https://doi.org/10.1051/epjconf/202124704024
Publication status	Published - 2020
MoE publication type	A4 Article in a conference publication
Event	International Conference on Physics of Reactors, PHYSOR 2020: Transition to a Scalable Nuclear Future - Cambridge, United Kingdom Duration: 28 Mar 2020 → 2 Apr 2020

Funding

This work has been funded from the McSAFE project which is receiving funding from the Euratom research and training program 20142018 under grant agreement No 755097.

Keywords

Monte Carlo
Serpent
Uniform Fission Source
Variance reduction

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10.1051/epjconf/202124704024Licence: CC BY

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title = "Effect of the uniform fission source method on local power variance in full core serpent calculation",

abstract = "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.",

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author = "Yurii Bilodid and Jaakko Lepp{\"a}nen",

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AU - Leppänen, Jaakko

N1 - Funding Information: This work has been funded from the McSAFE project which is receiving funding from the Euratom research and training program 20142018 under grant agreement No 755097. Publisher Copyright: © The Authors, published by EDP Sciences. This is an open access article distributed under the terms of the Creative Commons Attribution License 4.0 (http://creativecommons.org/licenses/by/4.0/).

PY - 2020

Y1 - 2020

N2 - 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.

AB - 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.

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KW - Uniform Fission Source

KW - Variance reduction

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T2 - International Conference on Physics of Reactors, PHYSOR 2020

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ER -

Effect of the uniform fission source method on local power variance in full core serpent calculation

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