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Dive into the research topics where Andrew Splawski is active.

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Featured researches published by Andrew Splawski.


Volume 3: Thermal Hydraulics; Instrumentation and Controls | 2008

Computational Fluid Dynamics Modeling of Two-Phase Flow Topologies in a Boiling Water Reactor Fuel Assembly

Adrian Tentner; Simon Lo; Andrew Splawski; Andrey Ioilev; Vladimir Melnikov; Maskhud Samigulin; Vasily Ustinenko; Sufia Melnikova

This paper presents recent advances in the development and validation of the two-phase flow topology models implemented in CFD-BWR, an advanced Computational Fluid Dynamics (CFD) computer code that allows the detailed analysis of the two-phase flow and heat transfer phenomena in Boiling Water Reactor (BWR) fuel assemblies under various operating conditions. The local inter-phase surface topology plays a central role in determining the mass, momentum, and energy exchanges between the liquid and vapor phases and between the two-phase coolant and the fuel pin cladding. The paper describes the topology map used to determine the local inter-phase surface topology and the role of the local topology in determining the inter-phase mass, momentum, and energy transfer. It discusses the relationship between the local interphase surface topology and the traditional channel flow regimes and presents results of experiment analyses in which computed local topologies are aggregated into flow regimes and compared with experimental observations.Copyright


The Journal of Computational Multiphase Flows | 2012

The Importance of Correct Modeling of Bubble Size and Condensation in Prediction of Sub-Cooled Boiling Flows

Simon Lo; Andrew Splawski; B.J. Yun

This paper describes the updating of the sub-cooled boiling model used in CFD codes with the more recent and better sub-models. The improved sub-models include: Hibiki and Ishii [1] correlation for nucleation site density, Kocamustafaogullari [2] correlation for bubble departure diameter and the S-gamma model of Lo and Rao [3] for bubble size distribution in the flow. The new model has been tested against measured data from Debora [4] and Bartolomei [5]. The results show that improvement in the bubble size prediction has the most significant impact on the accuracy of the model.


Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition | 2008

Prediction of Boiling Water Reactor Assembly Void Distributions Using a Two-Phase Computational Fluid Dynamics Model

W. David Pointer; Adrian Tentner; Tanju Sofu; Simon Lo; Andrew Splawski

This paper presents recent results obtained as part of the on-going integral validation of an advanced Eulerian-Eulerian two-phase (E2P) computational fluid dynamics based boiling model that allows the detailed analysis of the two-phase flow and heat transfer phenomena in a Boiling Water Reactor (BWR) fuel assembly. The code is being developed as a customized module built on the foundation of the commercial CFD-code STAR-CD which provides general two-phase flow modeling capabilities. Simulations of a prototypic BWR fuel assembly experiment have been completed as an initial assessment of the applicability of the E2P model to realistic BWR geometries and conditions. Initial validation has focused on comparison with measured sub-channel averaged data to enable the benchmarking of the accuracy of the E2P against the current predictive capabilities of the sub-channel methods. The paper will discuss the effects of modeling assumptions, assumed coefficient values and the computational mesh structure used to describe the fuel assembly geometry on the accuracy of the sub-channel averaged void fraction.© 2008 ASME


Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control | 2009

Development and Validation of a Computational Fluid Dynamics Model for the Simulation of Two-Phase Flow Phenomena in a Boiling Water Reactor Fuel Assembly

Adrian Tentner; W. David Pointer; Simon Lo; Andrew Splawski

This paper presents the current status in the development and validation of an advanced Computational Fluid Dynamics (CFD) model, CFD-BWR, which allows the detailed analysis of the two-phase flow and heat transfer phenomena in Boiling Water Reactor (BWR) fuel assemblies under various operating conditions. The CFD-BWR model uses an Eulerian Two-Phase (E2P) approach, and is also referred to as the E2P modeling framework. It is being developed as a customized module built on the foundation of the commercial CFD-code STAR-CD which provides general two-phase flow modeling capabilities. The integral validation efforts have focused on the analysis of the NUPEC Full-Size Boiling Water Reactor Test (BFBT) within the framework of the OECD/NRC benchmark exercise. The paper reviews the two-phase models implemented in the CFD-BWR code, and emphasizes recently implemented models of inter-phase and coolant-cladding momentum and energy exchanges. Results of recent BFBT experiment simulations using these models are presented and the effects of the new models on the calculated void distribution are discussed. The paper concludes with a discussion of future model development and validation plans.Copyright


Turbulence and Interactions | 2015

Eulerian-Eulerian Large-Eddy Simulations in Bubble-Columns

Dimitrios Papoulias; Mohit Tandon; Andrew Splawski; Simon Lo

In this paper the Eulerian-Eulerian two-fluid model implemented in STAR-CCM+ is used to predict the turbulent mixing of a bubble-column flow. Calculations are performed using the Reynolds-averaged Navier-Stokes equations (RANS) and typical two-point turbulence closure models, as well as by means of large-eddy filtering techniques (LES), based on the Smalgorinsky subgrid-scale method (SGS). The bubble and fluid phases are coupled by integrating momentum exchange terms due to drag, lift and virtual-mass forces, while turbulent dispersion effects are also accounted. Validation of the multiphase Eulerian model is performed against available Laser Doppler Anemometry measurements (LDA), reported in the experimental work of Deen et al. (Chem Eng Sci 56: 6341–6349, 2001 [1]).


Nuclear Engineering and Design | 2012

Prediction of a subcooled boiling flow with advanced two-phase flow models

Byong-Jo Yun; Andrew Splawski; Simon Lo; Chul-Hwa Song


Canadian Journal of Chemical Engineering | 2015

Adaptive multiply size group method for CFD-population balance modelling of polydisperse flows

Alexander Vikhansky; Andrew Splawski


PHYSOR-2006 - American Nuclear Society's Topical Meeting on Reactor Physics | 2006

Extension of integrated neutronic and thermal-hydraulic analysis capabilities of the "numerical nuclear reactor" software system for BWR applications

D. Weber; T. Sofa; D. Pointer; Adrian Tentner; Z. Zhong; T. Downar; J. Thomas; Simon Lo; Andrew Splawski


Archive | 2013

Validation of numerical simulations of gas-liquid systems in a vertical pipe

Mohit P. Tandon; Abhishek Khanolkar; Andrew Splawski; Simon Lo


Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management | 2016

Simulation of Direct Contact Condensation Using Large Scale Interface Multifluid Model

Vinesh H. Gada; Mohit Tandon; Jebin Elias; Andrew Splawski; Simon Lo

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Adrian Tentner

Argonne National Laboratory

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W. David Pointer

Argonne National Laboratory

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Tanju Sofu

Argonne National Laboratory

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Byong-Jo Yun

Pusan National University

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David Weber

Seoul National University

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D. Pointer

Argonne National Laboratory

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D. Weber

Argonne National Laboratory

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