A data-driven framework for error estimation and mesh-model optimization in system-level thermal-hydraulic simulation

H Bao, NT Dinh, JW Lane, RW Youngblood - Nuclear Engineering and …, 2019 - Elsevier
Over the past decades, several computer codes have been developed for simulation and
analysis of thermal-hydraulics and system response in nuclear reactors under operating …

Deep learning interfacial momentum closures in coarse-mesh CFD two-phase flow simulation using validation data

H Bao, J Feng, N Dinh, H Zhang - International Journal of Multiphase Flow, 2021 - Elsevier
Multiphase flow phenomena have been widely observed in the industrial applications, yet it
remains a challenging unsolved problem. Three-dimensional computational fluid dynamics …

Accident mitigation for spent fuel storage in the upper pool of a Mark III containment

YS Chen, YR Yuann - Annals of Nuclear Energy, 2016 - Elsevier
The upper pool (UP) is a specific design of the Mark III containments. Basically, no fuel can
be stored in the UP when the reactor criticality is achieved. The Kuosheng plant in Taiwan …

Evaluation of cooling capacity with more fuel stored in the spent fuel pool of the Kuosheng plant

YS Chen, YR Yuann - Annals of Nuclear Energy, 2017 - Elsevier
The storage capacity of the spent fuel pool (SFP) of the Kuosheng plant will be insufficient in
recent years. Fuel racks are suggested to be installed in the cask loading pool to increase …

A Strongly Coupled Reactor Core Isolation Cooling System Model for Extended Station Black-Out Analyses

H Zhao, H Zhang, L Zou, RC Martineau - 2015 - osti.gov
The reactor core isolation cooling (RCIC) system in a boiling water reactor (BWR) provides
makeup cooling water to the reactor pressure vessel (RPV) when the main steam lines are …

[图书][B] Development of a Data-driven Framework for Mesh-Model Optimization in System-level Thermal-Hydraulic Simulation

H Bao - 2018 - search.proquest.com
Over the past decades, several computer codes were developed for simulation and analysis
of thermal-hydraulics of reactor cores, reactor coolant systems, and containment behaviors …

[DOC][DOC] Simulation of BWR Mark I Station Black-Out accident using GOTHIC: an initial demonstration

H Bao, H Zhao, H Zhang, L Zou, R Szilard… - 2015 ANS Winter …, 2015 - researchgate.net
The Fukushima Daiichi nuclear disaster occurred on March 11, 2011. The seismic event and
following tsunami brought an extended Station Black-Out (SBO) accident.[1] In order to …

[图书][B] Feature Similarity Measurement Application in Global Extrapolation through Local Interpolation Condition

Y Sun - 2020 - search.proquest.com
Data-driven error-estimation method is a physics-guided data-driven approach for
quantifying uncertainties in system thermal-hydraulic (STH) simulation by low-fidelity …