TY - JOUR
T1 - Effect of the uniform fission source method on local power variance in full core serpent calculation
AU - Bilodid, Yurii
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.
KW - Monte Carlo
KW - Serpent
KW - Uniform Fission Source
KW - Variance reduction
UR - http://www.scopus.com/inward/record.url?scp=85108441212&partnerID=8YFLogxK
U2 - 10.1051/epjconf/202124704024
DO - 10.1051/epjconf/202124704024
M3 - Article in a proceedings journal
AN - SCOPUS:85108441212
VL - 247
SP - 871
EP - 878
JO - EPJ Web of Conferences
JF - EPJ Web of Conferences
SN - 2101-6275
T2 - International Conference on Physics of Reactors, PHYSOR 2020
Y2 - 28 March 2020 through 2 April 2020
ER -