Abstract

In this paper the use of machine learning (ML) is explored as an efficient tool for uncertainty quantification. A machine learning algorithm is developed to predict the peak cladding temperature (PCT) under the conditions of a large break loss of coolant accident given the various underlying uncertainties. The best estimate approach is used to simulate the thermal-hydraulic system of APR1400 large break loss of coolant accident (LBLOCA) scenario using the multidimensional reactor safety analysis code (MARS-KS) lumped parameter system code developed by Korea Atomic Energy Research Institute (KAERI). To generate the database necessary to train the ML model, a set of uncertainty parameters derived from the phenomena identification and ranking table (PIRT) is propagated through the thermal hydraulic model using the Dakota-MARS uncertainty quantification framework. The developed ML model uses the database created by the uncertainty quantification framework along with Keras library and Talos optimization to construct the artificial neural network (ANN). After learning and validation, the ML model can predict the peak cladding temperature (PCT) reasonably well with a mean squared error (MSE) of ∼0.002 and R2 of ∼0.9 with 9 to 11 key uncertain parameters. As a bounding accident scenario analysis of the LBLOCA case paves the way to using machine learning as a decision making tool for design extension conditions as well as severe accidents.

Highlights

  • Deterministic safety analysis has traditionally been utilized to demonstrate the robustness of nuclear power plants, usually adopting a conservative approach

  • The thermal hydraulic system response is validated against values reported in the APR1400 Design Control Document (DCD) (KHNP, 2014) for both steady state and transient simulations

  • The artificial neural network (ANN) algorithm has been successfully developed and trained using the database created via the uncertainty quantification framework

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Summary

Introduction

Deterministic safety analysis has traditionally been utilized to demonstrate the robustness of nuclear power plants, usually adopting a conservative approach. The best estimate (BE) approach provides a more realistic system response based on detailed thermal-hydraulic mechanistic models provided it is accompanied with uncertainty quantification (UQ). The integration of BE and UQ is known as best estimate plus uncertainty (BEPU) and is built upon a statistical foundation to provide a more realistic estimation of the safety margin and ensure that the safety limit is met. Utilities were given an ample opportunity to apply the best estimate plus uncertainty (BEPU) methodology following the United States Regulatory Commission (USNRC) amendment of 10CFR50.46 Appendix-K in 1988.

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