Tree-Based Ensemble Learning Models for Wall Temperature Predictions in Post-Critical Heat Flux Flow Regimes at Subcooled and Low-Quality Conditions

Author:

Liu Qingqing12,Liu Yang34,Burak Adam5,Kelly Joseph6,Bajorek Stephen6,Sun Xiaodong5

Affiliation:

1. Department of Nuclear Engineering and Radiological Sciences, University of Michigan , Ann Arbor, MI 48109-2104 ; 10621-J Iron Bridge Road, Jessup, MD 20794

2. Dynaflow, Incorporated , Ann Arbor, MI 48109-2104 ; 10621-J Iron Bridge Road, Jessup, MD 20794

3. Department of Nuclear Engineering and Radiological Sciences, University of Michigan , Ann Arbor, MI 48109-2104 ; , Lemont, IL 60439

4. Nuclear Science and Engineering Division, Argonne National Laboratory , Ann Arbor, MI 48109-2104 ; , Lemont, IL 60439

5. Department of Nuclear Engineering and Radiological Sciences, University of Michigan , Ann Arbor, MI 48109-2104

6. Office of Nuclear Regulatory Research, The U.S. Nuclear Regulatory Commission , Washington, DC 20555-0001

Abstract

Abstract Accurately predicting post-critical heat flux (CHF) heat transfer is an important but challenging task in water-cooled reactor design and safety analysis. Although numerous heat transfer correlations have been developed to predict post-CHF heat transfer, these correlations are only applicable to relatively narrow ranges of flow conditions due to the complex physical nature of the post-CHF heat transfer regimes. In this paper, a large quantity of experimental data is collected and summarized from the literature for steady-state subcooled and low-quality film boiling regimes with water as the working fluid in vertical tubular test sections. A low-quality water film boiling (LWFB) database is consolidated with a total of 22,813 experimental data points, which cover a wide flow range of the system pressure from 0.1 to 9.0 MPa, mass flux from 25 to 2750 kg/m2 s, and inlet subcooling from 1 to 70 °C. Two machine learning (ML) models, based on random forest (RF) and gradient boosted decision tree (GBDT), are trained and validated to predict wall temperatures in post-CHF flow regimes. The trained ML models demonstrate significantly improved accuracies compared to conventional empirical correlations. To further evaluate the performance of these two ML models from a statistical perspective, three criteria are investigated and three metrics are calculated to quantitatively assess the accuracy of these two ML models. For the full LWFB database, the root-mean-square errors between the measured and predicted wall temperatures by the GBDT and RF models are 5.7% and 6.2%, respectively, confirming the accuracy of the two ML models.

Funder

U.S. Nuclear Regulatory Commission

Publisher

ASME International

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