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

Direct numerical simulation of reactor two-phase flows enabled by high-performance computing

Fang, J., Cambareri, J. J., Brown, C. S., Feng, J. Y., Gouws, A., Li, M. N., & Bolotnov, I. A. (2018), Nuclear Engineering and Design, 330, 409–419.

Effect of the wall presence on the bubble interfacial forces in a shear flow field

Feng, J. Y., & Bolotnov, I. A. (2018), International Journal of Multiphase Flow, 99, 73–85.

Numerical comparison of bubbling in a waste glass melter

Guillen, D. P., Cambareri, J., Abboud, A. W., & Bolotnov, I. A. (2018), Annals of Nuclear Energy, 113, 380–392.

Bubble tracking analysis of PWR two-phase flow simulations based on the level set method

Fang, J., & Bolotnov, I. A. (2017), Nuclear Engineering and Design, 323, 68–77.

Coalescence prevention algorithm for level set method

Talley, M. L., Zimmer, M. D., & Bolotnov, I. A. (2017), Journal of Fluids Engineering-Transactions of the ASME, 139(8).

Evaluation of bubble-induced turbulence using direct numerical simulation

Feng, J. Y., & Bolotnov, I. A. (2017), International Journal of Multiphase Flow, 93, 92–107.

High current C-11 gas target design and optimization using multi-physics coupling

Peeples, J. L., Magerl, M., O’Brien, E. M., Doster, J. M., Bolotnov, I. A., Wieland, B. W., & Stokely, M. H. (2017), In Wttc16: proceedings of the 16th international workshop on targetry and target chemistry (Vol. 1845).

Interface tracking simulations of bubbly flows in PWR relevant geometries

Fang, J., Rasquin, M., & Bolotnov, I. A. (2017), Nuclear Engineering and Design, 312, 205–213.

Interfacial force study on a single bubble in laminar and turbulent flows

Feng, J. Y., & Bolotnov, I. A. (2017), Nuclear Engineering and Design, 313, 345–360.

Wall-resolved spectral cascade-transport turbulence model

Brown, C. S., Shaver, D. R., Lahey, R. T., & Bolotnov, I. A. (2017), Nuclear Engineering and Design, 320, 309–324.

Spectral analysis of single- and two-phase bubbly DNS in different geometries

Brown, C. S., & Bolotnov, I. A. (2016), Nuclear Science and Engineering, 184(3), 363–376.

DNS of turbulent flow with hemispherical wall roughness

Mishra, A. V., & Bolotnov, I. A. (2015), Journal of Turbulence, 16(3), 225–249.

Estimation of shear-induced lift force in laminar and turbulent flows

Thomas, A. M., Fang, J., Feng, J. Y., & Bolotnov, I. A. (2015), Nuclear Technology, 190(3), 274–291.

Coupled DNS/RANS simulation of fission gas discharge during loss-of-flow accident in generation IV sodium fast reactor

Behafarid, F., Shaver, D., Bolotnov, I. A., Antal, S. P., Jansen, K. E., & Podowski, M. Z. (2013), (Vol. 181, pp. 44–55).

Influence of bubbles on the turbulence anisotropy

Bolotnov, I. A. (2013), Journal of Fluids Engineering-Transactions of the ASME, 135(5).

Influence of bubbles on the turbulence anisotropy

Bolotnov, I. A. (2012), In Proceedings of the asme fluids engineering division summer meeting, 2012, vol 1, pts a and b, symposia (pp. 695–702).

Multidimensional analysis of fission gas transport following fuel element failure in sodium fast reactor

Bolotnov, I. A., Antal, S. P., Jansen, K. E., & Podowski, M. Z. (2012), Nuclear Engineering and Design, 247, 136–146.

Detached direct numerical simulations of turbulent two-phase bubbly channel flow

Bolotnov, I. A., Jansen, K. E., Drew, D. A., Oberai, A. A., Lahey, R. T., & Podowski, M. Z. (2011), International Journal of Multiphase Flow, 37(6), 647–659.

View all publications via NC State Libraries

Grants

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 - 12/31/18)

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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: 12/31/18

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 - 9/30/19)

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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: 9/30/19

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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Academic Career Development For a Nuclear Engineering Junior Faculty at North Carolina State University

US Nuclear Regulatory Commission(4/01/12 - 3/31/16)

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Academic Career Development For a Nuclear Engineering Junior Faculty at North Carolina State University

Sponsor: US Nuclear Regulatory Commission

Start Date: 4/01/12

End Date: 3/31/16

Abstract

Over the past four years the Department of Nuclear Engineering at North Carolina State University has undergone aggressive growth, almost doubling the number of active faculty from eight in Summer 2007 to fifteen this semester, with one open junior position still in search. Among the new faculty added within this span of time three are senior faculty (including the Department Head) and five are junior faculty. [One Associate Professor, Dr. Man-Sung Yim resigned his position to become Department Head at KAIST, Korea]. With these additions the Department holds an excellent strategic position within the nuclear engineering education community due to its rejuvenated ranks and the ongoing smooth generational transition of its faculty with senior members mentoring the careers of junior members. However, the ongoing economic crisis and the decline of funding from the State of North Carolina are raising concerns that recruiting a highly qualified candidate to the open position currently in search and nurturing his/her academic career once hired will not be affordable. The goal of the academic development program proposed here is to assemble an attractive package to help the Department recruit a top-notch candidate in the area of nuclear power and to provide them a reliable resource to supplement the standard startup package in growing their career. The hired faculty member will be mentored by senior faculty in the Department, and will be afforded advice on means to best utilize this combination of standard and supplementary resources to propel their academic career towards success. The benefit to the faculty member will be realized when he/she eventually receives tenure thus consolidating their academic career path and embarking on the next stage by preparing for promotion to a higher rank. The benefit to the Department is the ability to attract top talent to apply for the open position, and to retain them in an academic career once hired. The benefit to the fields of nuclear science and engineering is to replenish and rejuvenate the cadre of academicians who will shape the future of nuclear energy in the US and globally through their research and by educating a new generation of nuclear professionals essential to implementing the nation?s nuclear agendas.

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Simulation of Turbulent Multiphase Flows For Nuclear Reactor Safety

US Dept. of Energy (DOE)(1/01/12 - 12/31/14)

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Simulation of Turbulent Multiphase Flows For Nuclear Reactor Safety

Sponsor: US Dept. of Energy (DOE)

Start Date: 1/01/12

End Date: 12/31/14

Abstract

Direct numerical simulation of turbulent bubbly two-phase flows at a leadership computing facility allows to obtain an unprecedented level of turbulent two-phase flow resolution and can answer fundamental questions about the interaction between the bubbles and the liquid turbulence. This knowledge will be used to improve the safety of light water nuclear reactors.

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Consortium for Advanced Simulations for Light Water Reactors (CASL) - Oak Ridge National laboratory

US Dept. of Energy (DOE)(11/30/-1 - 9/30/19)

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Consortium for Advanced Simulations for Light Water Reactors (CASL) - Oak Ridge National laboratory

Sponsor: US Dept. of Energy (DOE)

Start Date: 11/30/-1

End Date: 9/30/19

Abstract

The Consortium for Advanced Simulation of Light Water Reactors, CASL, supports the broad national missions of enabling energy independence; supporting economic growth through the offering of superior technology ; and being good stewards of the environment, buy enabling predictive simulation of nuclear power plants. Such capability will make possible power uprates, lifetime extension and higher fuel burnups for currently operating and new Generation III+ nuclear power plants.

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