Education

Research Description

Dr. Bolotnov is interested in using multiscale approaches for nuclear reactor simulations, development of new spectral cascade transfer multiphase flow turbulence models, and direct numerical simulation of single and multiphase turbulent flows.

Publications

Two-Phase Turbulence Statistics from High Fidelity Dispersed Droplet Flow Simulations in a Pressurized Water Reactor (PWR) Sub-Channel with Mixing Vanes

Saini, N., & Bolotnov, I. A. (2021), FLUIDS, 6(2). https://doi.org/10.3390/fluids6020072

Annular Flow Simulation Supported by Iterative In-Memory Mesh Adaptation

Fang, J., Purser, M. K., Smith, C., Balakrishnan, R., Bolotnov, I. A., & Jansen, K. E. (2020), NUCLEAR SCIENCE AND ENGINEERING. https://doi.org/10.1080/00295639.2020.1743577

Exploring Two-Phase Flow Regime Transition Mechanisms Using High-Resolution Virtual Experiments

Zimmer, M. D., & Bolotnov, I. A. (2020), NUCLEAR SCIENCE AND ENGINEERING. https://doi.org/10.1080/00295639.2020.1722543

Interface capturing simulations of bubble population effects in PWR subchannels

Cambareri, J. J., Fang, J., & Bolotnov, I. A. (2020), NUCLEAR ENGINEERING AND DESIGN, 365. https://doi.org/10.1016/j.nucengdes.2020.110709

Interface-Resolved Simulations of Reactor Flows

Fang, J., Cambareri, J. J., Li, M., Saini, N., & Bolotnov, I. A. (2020). [Review of , ]. NUCLEAR TECHNOLOGY, 206(2), 133–149. https://doi.org/10.1080/00295450.2019.1620056

Machine-learning based error prediction approach for coarse-grid Computational Fluid Dynamics (CG-CFD)

Hanna, B. N., Dinh, N. T., Youngblood, R. W., & Bolotnov, I. A. (2020), PROGRESS IN NUCLEAR ENERGY, 118. https://doi.org/10.1016/j.pnucene.2019.103140

Simulation scaling studies of reactor core two-phase flow using direct numerical simulation

Cambareri, J. J., Fang, J., & Bolotnov, I. A. (2020, March), NUCLEAR ENGINEERING AND DESIGN, Vol. 358. https://doi.org/10.1016/j.nucengdes.2019.110435

The evaporation and condensation model with interface tracking

Li, M., & Bolotnov, I. A. (2020), INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 150. https://doi.org/10.1016/j.ijheatmasstransfer.2019.119256

Development of a New Contact Angle Control Algorithm for Level-Set Method

Li, M., Zeng, K., Wonnell, L., & Bolotnov, I. A. (2019), JOURNAL OF FLUIDS ENGINEERING-TRANSACTIONS OF THE ASME, 141(6). https://doi.org/10.1115/1.4041987

Slug-to-churn vertical two-phase flow regime transition study using an interface tracking approach

Zimmer, M. D., & Bolotnov, I. A. (2019), INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, 115, 196–206. https://doi.org/10.1016/j.ijmultiphaseflow.2019.04.003

View all publications via NC State Libraries

Grants

Multiple Bubble Boiling Simulation Scaling and Evaluation

US Dept. of Energy (DOE)(9/08/20 - 11/30/20)

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Multiple Bubble Boiling Simulation Scaling and Evaluation

Sponsor: US Dept. of Energy (DOE)

Start Date: 9/08/20

End Date: 11/30/20

Abstract

The proposed high resolution simulation efforts will evaluate the boiling capabilities in different pressure conditions and compare the results with existing models, experiments and previously published simulations. The work will evaluate the interface capturing approach capabilities for the problems of interest and will provide the recommendations about requirements and future research to expand those capabilities.

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Center for thermal-fluids application in nuclear energy: Establishing the knowledge base for thermal-hydraulic multiscale simulation to accelerate the deployment of advanced reactors.

US Dept. of Energy (DOE)(10/01/20 - 9/30/23)

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Center for thermal-fluids application in nuclear energy: Establishing the knowledge base for thermal-hydraulic multiscale simulation to accelerate the deployment of advanced reactors.

Sponsor: US Dept. of Energy (DOE)

Start Date: 10/01/20

End Date: 9/30/23

Abstract

In this DOE-funded project the NCSU team will support the larger effort in establishing the knowledgebase for thermal-hydraulic multiscale simulation to accelerate the deployment of advanced reactors. NCSU focus will be on performing high resolution simulations of advanced reactor flows as well as developing advanced methodologies for data processing using machine-learning techniques.

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Pilot Study on Two-Phase flow DNS Application to Heat Transfer Enhancement Pipe

Mitsubishi Heavy Industries, Ltd.(7/01/20 - 12/31/20)

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Pilot Study on Two-Phase flow DNS Application to Heat Transfer Enhancement Pipe

Sponsor: Mitsubishi Heavy Industries, Ltd.

Start Date: 7/01/20

End Date: 12/31/20

Abstract

Finite-element based flow solver (PHASTA) [1] [2] [3] with Level-Set method for interface tracking is proposed to perform bubble/flow interaction studies. This code has been successfully applied to large scale direct numerical simulation (DNS) of turbulent flows in various geometries, as well as interface tracking simulations (including bubbly channel flow [4] [5], annular flow [6], reactor geometry flows [7], Fig. 1). Flexible data analysis tools have been developed to quantify turbulence parameters [8] [9], including spectral information [10] and will be further improved to satisfy the needs of the proposed study. This set of tools was recently used by the PI-Bolotnov to quantify the influence of bubbles on the turbulence anisotropy in a channel [11]. It has been demonstrated that the controlled-bubble approach is validated [12], drag and lift force can be evaluated [13], bubble-induced turbulence can be evaluated [14] and the wall-effects on the interfacial forces can be studied [15].

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Computationally Efficient Prediction of Containment Thermal Hydraulics Using Multi-Scale Simulation

US Dept. of Energy (DOE)(11/21/16 - 9/30/18)

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Computationally Efficient Prediction of Containment Thermal Hydraulics Using Multi-Scale Simulation

Sponsor: US Dept. of Energy (DOE)

Start Date: 11/21/16

End Date: 9/30/18

Abstract

Analysis of containment phenomena requires addressing three-dimensional (3D) phenomena over large length scales, making existing high-quality Computational Fluid dynamics (CFD) techniques infeasible. The project objective is to develop a coarse-grained (CG) CFD capability to make sufficiently high-fidelity analysis of containment thermal-hydraulics feasible. The project will evaluate feasibility of a data-driven multi-scale framework to enable computationally efficient simulation of containment thermal-hydraulic processes. Through two case studies, the project will investigate (1) applicability of scale separation and mixing length hypotheses, (2) the effect of mesh size on solution, (3) error recovery through data-driven sub-grid-scale (SGS) models, (4) identifiability and dimensionless characterization of 3D flow patterns, and (5) Bayesian calibration of a SGS model on high-fidelity flow field data. Based on insights gained, the project will formulate a framework for data-driven multiscale simulation, recommendations for high-fidelity CFD data archiving, classification, mining, and assimilation, and requirements for construction of surrogate SGS models

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Research and Technical Assistance Related to Severe Accidents in Nuclear Power Plants

US Nuclear Regulatory Commission(9/08/16 - 6/30/19)

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Research and Technical Assistance Related to Severe Accidents in Nuclear Power Plants

Sponsor: US Nuclear Regulatory Commission

Start Date: 9/08/16

End Date: 6/30/19

Abstract

A team of researchers led by the University of Wisconsin-Madison (UW), and comprising Texas A&M University (TAMU), California Institute of Technology (CalTech), and North Carolina State University (NCSU) is proposing to establish a university-based center focused on severe accident research and technical assistance. Our team’s research objectives are to: (i) conduct research in severe accident phenomena, in particular, those phenomena where residual uncertainties remain in light of Fukushima, and reduction of such uncertainties is warranted to address high priority Near-Term Task Force (NTTF) recommendations; (ii) provide technical assistance to the NRC related to post Fukushima safety and severe accident research; and (3) develop and maintain a repository of knowledge in severe accident research. Specific areas of technical assistance in which the center has substantial expertise and experience include in-vessel core heatup and core degradation phenomena; ex-vessel phenomena, including fuel-coolant interactions and core-concrete interactions; hydrogen mixing, combustion and control strategies; reactor system behavior under beyond-design basis conditions, and advanced modeling techniques, including reactor systems modeling and Computational Fluid Dynamics (CFD) methods that can be used in severe accident evaluation.

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Computationally Efficient Prediction of Containment Thermal Hydraulics Using Multi-Scale Simulation: Feasibility Study (FY 16 NUC)

US Dept. of Energy (DOE)(12/23/15 - 9/30/16)

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Computationally Efficient Prediction of Containment Thermal Hydraulics Using Multi-Scale Simulation: Feasibility Study (FY 16 NUC)

Sponsor: US Dept. of Energy (DOE)

Start Date: 12/23/15

End Date: 9/30/16

Abstract

The project technical objective is to develop and evaluate feasibility of a technical basis for the coarse-grained (CG) CFD capability that is needed for high-fidelity analysis of containment thermal-hydraulics. Specifically, the project will investigate a data-driven multi-scale framework having the potential to enable computationally efficient simulation of containment thermal-hydraulic processes.

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Development and Application of a Data-Driven Methodology for Validation of Risk Informed Safety Margin Characterization Models

US Dept. of Energy (DOE)(10/01/16 - 12/30/20)

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Development and Application of a Data-Driven Methodology for Validation of Risk Informed Safety Margin Characterization Models

Sponsor: US Dept. of Energy (DOE)

Start Date: 10/01/16

End Date: 12/30/20

Abstract

This project will develop methodology for verification and validation of advanced computer models used in Risk-Informed Safety Margin Characterization (RISMC) of nuclear power plants. The project will apply the methodology to selected problems in nuclear reactor safety. The focus is placed on computer codes that simulate external hazards that have impact on plant safety, including severe accident management and emergency response. The project will collect, characterize, archive, and use data from plant measurements, integral-effect and separate-effect tests to support code validation. The methodology will bring to use probabilistic risk assessment (PRA) to guide a risk-informed validation approach implementation.

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Development and Validation of a Societal Risk Goal for Nuclear Power Plant Safety (2014-2015)

US Dept. of Energy (DOE)(11/04/14 - 9/30/15)

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Development and Validation of a Societal Risk Goal for Nuclear Power Plant Safety (2014-2015)

Sponsor: US Dept. of Energy (DOE)

Start Date: 11/04/14

End Date: 9/30/15

Abstract

Quantification of nuclear power plant safety risk requires a systematic and yet practical approach to identification of accident scenarios, assessment of their likelihood and consequences. Instrumental to this goal is risk-informed safety margin characterization (RISMC) framework, whose realization requires computationally robust and affordable methods for sufficiently accurate simulation of complex multi-dimensional physical phenomena, such as turbulent and multi-phase flow.

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Turbulent Multiphase Flows for Nuclear Reactor Safety.

US Dept. of Energy (DOE) - Advanced Scientific Computing Research (ASCR)(7/01/14 - 6/30/15)

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Turbulent Multiphase Flows for Nuclear Reactor Safety.

Sponsor: US Dept. of Energy (DOE) - Advanced Scientific Computing Research (ASCR)

Start Date: 7/01/14

End Date: 6/30/15

Abstract

This project will perform direct numerical simulation of turbulent, bubbly, two-phase flows, allowing for an unprecedented level of detail and, potentially, answers to fundamental questions about the interaction between the bubbles and the liquid turbulence. This knowledge will provide new information about the bubble's influence on the turbulence.

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Simulation and Modeling of the Interactions of Liquid Turbulent Eddies and Gas Bubbles

National Science Foundation (NSF)(7/15/13 - 6/30/17)

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Simulation and Modeling of the Interactions of Liquid Turbulent Eddies and Gas Bubbles

Sponsor: National Science Foundation (NSF)

Start Date: 7/15/13

End Date: 6/30/17

Abstract

The objective of the proposed research is to quantify bubble/turbulence interactions in a wide variety of flow conditions by analyzing experimentally validated interface tracking simulations and developing new turbulence-spectrum aware interfacial force models for CMFD and multiphase large-eddy simulations (LES). Fundamental understanding of forces governing bubble/turbulence interactions is a major key to the new generation of multiphase CFD and LES models which will allow virtual testing and design of multiphase flow systems.

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