Abstract

Best estimate plus uncertainty is the leading methodology to validate existing safety margins. It remains a challenge to develop and license these approaches, in part due to the high dimensionality of system codes. Uncertainty quantification is an active area of research to develop appropriate methods for propagating uncertainties, offering greater scientific reason, dimensionality reduction and minimising reliance on expert judgement. Inverse uncertainty quantification is required to infer a best estimate back on the input parameters and reduce the uncertainties, but it is challenging to capture the full covariance and sensitivity matrices. Bayesian inverse strategies remain attractive due to their predictive modelling and reduced uncertainty capabilities, leading to dramatic model improvements and validation of experiments. This paper uses state-of-the-art data assimilation techniques to obtain a best estimate of parameters critical to plant safety. Data assimilation can combine computational, benchmark and experimental measurements, propagate sparse covariance and sensitivity matrices, treat non-linear applications and accommodate discrepancies. The methodology is further demonstrated through application to hot zero power tests in a pressurised water reactor (PWR) performed using the BEAVRS benchmark with Latin hypercube sampling of reactor parameters to determine responses. WIMS 11 (dv23) and PANTHER (V.5:6:4) are used as the coupled neutronics and thermal-hydraulics codes; both are used extensively to model PWRs. Results demonstrate updated best estimate parameters and reduced uncertainties, with comparisons between posterior distributions generated using maximum entropy principle and cost functional minimisation techniques illustrated in recent conferences. Future work will improve the Bayesian inverse framework with the introduction of higher-order sensitivities.

Highlights

  • Despite decades of research, nuclear data contains large uncertainties that are crucial for accurate predictions of reactor analysis and beyond design basis fault studies

  • Predictive modelling and uncertainty quantification are an active area of research to improve results

  • This paper explores the use of data assimilation which has experienced a resurgence due to increased computational power and accounts for all the available experimental information and coupled simulations

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Summary

INTRODUCTION

Nuclear data contains large uncertainties that are crucial for accurate predictions of reactor analysis and beyond design basis fault studies. This paper explores the use of data assimilation which has experienced a resurgence due to increased computational power and accounts for all the available experimental information and coupled simulations. It has an established history in the nuclear industry through cross-section adjustments to generate evaluated nuclear data files. The broader aim of future research is to make improved predictions of largescale problems, demonstrate the impact of higher-order sensitivities and model adjustments with a particular interest on uncertainty reduction of model parameters

DATA ASSIMILATION OVERVIEW
Accounting for Model Error
HOT ZERO POWER TESTS
First-order uncertainty reductions on input parameters
CONCLUSIONS
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