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Background <p>The safety of nuclear facilities (NFs) should be justified using qualified software tools. However, the procedure for validating thermal-hydraulic computer codes requires assessing the uncertainty and sensitivity of calculation results.</p> Aim <p>To develop a&#xa0;technique for the correct and effective sensitivity analysis during the validation of thermal-hydraulic computer codes.</p> Materials and methods <p>For calculations, the KORSAR thermal-hydraulic code developed by the Alexandrov Research Institute of Technology (Sosnovy Bor, Russian Federation) was used; data of experiments on the true volumetric void fraction of subcooled pipe boiling (experiments of G.G.&#xa0;Bartolomei) were used for validation.</p> Results and discussion <p>The test calculations showed and justified the following necessary condition for the correctness of sensitivity analysis results: the input uncertainties set in the analysis of statistical characteristics should be equal. The performed study demonstrated the admissibility of excluding the input uncertain factors with the Spearman’s rank correlation coefficient less than |0.2| from the uncertainty analysis. This solution reduces labor costs for analyzing uncertainty.</p> Conclusion <p>The efficiency of validating thermal-hydraulic computer codes can be increased by conducting a&#xa0;preliminary sensitivity analysis before the formation of validation matrices, as well as by excluding minor input uncertainties from the detailed quantitative assessment of statistical characteristics.</p>

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Effects of input uncertainty characteristics on the statistical analysis of thermal-hydraulic calculations

  • 期刊论文

  • 发表日期：

    2026年5月20日

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  • V. A. Vasilenko,
  • Yu. A. Migrov,
  • A. V. Mitskevich,
  • A. V. Yarushin,
  • A. S. Gritsai

摘要

Background

The safety of nuclear facilities (NFs) should be justified using qualified software tools. However, the procedure for validating thermal-hydraulic computer codes requires assessing the uncertainty and sensitivity of calculation results.

Aim

To develop a technique for the correct and effective sensitivity analysis during the validation of thermal-hydraulic computer codes.

Materials and methods

For calculations, the KORSAR thermal-hydraulic code developed by the Alexandrov Research Institute of Technology (Sosnovy Bor, Russian Federation) was used; data of experiments on the true volumetric void fraction of subcooled pipe boiling (experiments of G.G. Bartolomei) were used for validation.

Results and discussion

The test calculations showed and justified the following necessary condition for the correctness of sensitivity analysis results: the input uncertainties set in the analysis of statistical characteristics should be equal. The performed study demonstrated the admissibility of excluding the input uncertain factors with the Spearman’s rank correlation coefficient less than |0.2| from the uncertainty analysis. This solution reduces labor costs for analyzing uncertainty.

Conclusion

The efficiency of validating thermal-hydraulic computer codes can be increased by conducting a preliminary sensitivity analysis before the formation of validation matrices, as well as by excluding minor input uncertainties from the detailed quantitative assessment of statistical characteristics.