Development of a transient critical power ratio methodology for cycle specific BWR reload analysis

• Developed a new methodology and framework for hot channel transient critical power ratio calculations for modern boiling water reactor fuel assemblies. • Extensive verification and validation of the framework conducted. • Demonstration case provided to illustrate the capabilities. A new framework for generic hot channel transient CPR computations for modern BWR fuel assemblies has been developed with the goal of providing comprehensive independent safety assessments for BWR reload licensing analysis. TRAnsient Cpr analysis Tool (TRACT) is implemented in Python 3, and acts as a wrapper to calculate the critical CPR condition using TRACE as a hot channel code with initial and boundary conditions taken from upstream S3K simulations. TRACT supports subprocess-based (multi-processor) parallelism and MPI parallel execution, such that the transient CPR analyses for a typical BWR reload can be completed within minutes. Using object-oriented code design, new dryout correlations, fuel designs and even new hot channel codes can be introduced using a clean API, with minimal effort, and with little risk of breaking the existing code. The approach also makes it extremely simple to create unit tests for V&V. The V&V of TRACT is an ongoing process. While verification of the implemented correlations has been carried out, basic unit tests have been established, and selected validation has been conducted, this will be continuously extended in the future. A demonstration case has been presented to illustrate the capabilities of the code. Despite independent codes, models and methodologies, transient CPR predictions using TRACT are consistent with vendor results.

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Publication Details

Journal
Annals of Nuclear Energy
Published
2025-09-25
DOI
https://doi.org/10.1016/j.anucene.2025.111902
Primary Topic
Nuclear reactor physics and engineering
Type
article
Field-Weighted Citation Impact
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article

Development of a transient critical power ratio methodology for cycle specific BWR reload analysis

Mitch Wolff, A. Gorzel, Jan Dus, Hakim Ferroukhi et al.
Annals of Nuclear Energy
Nuclear reactor physics and engineering
article

Development of a transient critical power ratio methodology for cycle specific BWR reload analysis

Mitch Wolff, A. Gorzel, Jan Dus, Hakim Ferroukhi, Ivor Clifford, Alexey Cherezov, Konstantin Nikitin
article en

Abstract

• Developed a new methodology and framework for hot channel transient critical power ratio calculations for modern boiling water reactor fuel assemblies. • Extensive verification and validation of the framework conducted. • Demonstration case provided to illustrate the capabilities. A new framework for generic hot channel transient CPR computations for modern BWR fuel assemblies has been developed with the goal of providing comprehensive independent safety assessments for BWR reload licensing analysis. TRAnsient Cpr analysis Tool (TRACT) is implemented in Python 3, and acts as a wrapper to calculate the critical CPR condition using TRACE as a hot channel code with initial and boundary conditions taken from upstream S3K simulations. TRACT supports subprocess-based (multi-processor) parallelism and MPI parallel execution, such that the transient CPR analyses for a typical BWR reload can be completed within minutes. Using object-oriented code design, new dryout correlations, fuel designs and even new hot channel codes can be introduced using a clean API, with minimal effort, and with little risk of breaking the existing code. The approach also makes it extremely simple to create unit tests for V&V. The V&V of TRACT is an ongoing process. While verification of the implemented correlations has been carried out, basic unit tests have been established, and selected validation has been conducted, this will be continuously extended in the future. A demonstration case has been presented to illustrate the capabilities of the code. Despite independent codes, models and methodologies, transient CPR predictions using TRACT are consistent with vendor results.

Annals of Nuclear EnergyVol. 226
Swiss Federal Nuclear Safety Inspectorate (CH)
Openalex Percentile: Top 66%
Nuclear reactor physics and engineering
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Development of a transient critical power ratio methodology for cycle specific BWR reload analysis — Mitch Wolff, A. Gorzel, et al. · Annals of Nuclear Energy (2025) | TGRS Research Map | TGRS