Application of the PSI cycle check-up methodology for full-core Monte Carlo simulations verified using pin power estimates and validated for hot zero power conditions

Monte Carlo (MC) based neutron transport codes provide high-fidelity numerical solutions to problems beyond the modelling capabilities of conventional core simulation methods. However, performing core-follow calculations with MC codes remains challenging due to the necessity of incorporating thermal-hydraulic feedback and generating evolved fuel composition for the cycle of interest by taking into account the entire irradiation history of loaded fuel assemblies over previous cycles. Nevertheless, at PSI, the neutronic version of a cycle check-up methodology (CHUP) is under development to address this challenge. This methodology involves extracting operating conditions and nuclide compositions from validated reference deterministic core-follow models (CASMO5/SIMULATE5/SNF), subsequently generating MC neutron transport models for selected operating points. This article presents the verification and validation performed for a hot zero power operating condition of a Swiss pressurised water reactor using the updated CHUP methodology, which automates information extraction from reference core models to minimise human intervention. The MC models were verified by assessing their deviation from criticality, consistently found to be supercritical within the [10,60] pcm range. Additionally, radial relative power distribution verification yield deviations in the [−5,4] % range compared to validated nodal results. Finally, additional validation was performed using start-up measurements from two successive cycles. Eight MC models were found to be subcritical, on average by 51 pcm, with a standard deviation of 25 pcm. • Enhancing PSI CHUP methodology focused on consistency with deterministic schemes. • Quantification of bias associated with introduced approximations. • Generation of full-core MC models at arbitrary reactor operating state-points. • Radial RPD verification yields deviations of [−5, 4]% vs. validated nodal results. • Validation vs. start-up measurements results in −51 ± 25 pcm deviations.

Authors

Institutions

Publication Details

Journal
Annals of Nuclear Energy
Published
2024-09-28
DOI
https://doi.org/10.1016/j.anucene.2024.110939
Citations
1
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
1.30

Funders

Controls
|||
ALL TIME
JAN
FEB
MAR
APR
MAY
JUN
JUL
AUG
SEP
OCT
article

Application of the PSI cycle check-up methodology for full-core Monte Carlo simulations verified using pin power estimates and validated for hot zero power conditions

Alexander Vasiliev, Matthias Frankl, Mathieu Hursin, Hakim Ferroukhi et al.
1 citations
Annals of Nuclear Energy
Nuclear reactor physics and engineering
1.30
article

Application of the PSI cycle check-up methodology for full-core Monte Carlo simulations verified using pin power estimates and validated for hot zero power conditions

Alexander Vasiliev, Matthias Frankl, Mathieu Hursin, Hakim Ferroukhi, D. Rochman, L. A. Berry
article en
1 citations

Abstract

Monte Carlo (MC) based neutron transport codes provide high-fidelity numerical solutions to problems beyond the modelling capabilities of conventional core simulation methods. However, performing core-follow calculations with MC codes remains challenging due to the necessity of incorporating thermal-hydraulic feedback and generating evolved fuel composition for the cycle of interest by taking into account the entire irradiation history of loaded fuel assemblies over previous cycles. Nevertheless, at PSI, the neutronic version of a cycle check-up methodology (CHUP) is under development to address this challenge. This methodology involves extracting operating conditions and nuclide compositions from validated reference deterministic core-follow models (CASMO5/SIMULATE5/SNF), subsequently generating MC neutron transport models for selected operating points. This article presents the verification and validation performed for a hot zero power operating condition of a Swiss pressurised water reactor using the updated CHUP methodology, which automates information extraction from reference core models to minimise human intervention. The MC models were verified by assessing their deviation from criticality, consistently found to be supercritical within the [10,60] pcm range. Additionally, radial relative power distribution verification yield deviations in the [−5,4] % range compared to validated nodal results. Finally, additional validation was performed using start-up measurements from two successive cycles. Eight MC models were found to be subcritical, on average by 51 pcm, with a standard deviation of 25 pcm. • Enhancing PSI CHUP methodology focused on consistency with deterministic schemes. • Quantification of bias associated with introduced approximations. • Generation of full-core MC models at arbitrary reactor operating state-points. • Radial RPD verification yields deviations of [−5, 4]% vs. validated nodal results. • Validation vs. start-up measurements results in −51 ± 25 pcm deviations.

Annals of Nuclear EnergyVol. 211
Paul Scherrer Institute (CH), École Polytechnique Fédérale de Lausanne (CH)
Paul Scherrer Institut
Affordable and clean energy
Openalex Percentile: Top 13%
Nuclear reactor physics and engineering
1.30
AI Navigator

Ask Laika to Summarize, Analyze, and Connect papers live on the map.

Summarize Papers & Methodologies

Extract key findings, datasets, and comparative methods across publications.

Benchmark Rankings & Visual Analytics

Rank top research institutions, authors, funders, topics, and journals by Field-Weighted Citation Impact (FWCI) and paper volume with instant charts.

Connect Distant Disciplines

Bridge topological clusters on the map to find hidden collaborative intersections.