Education

Research Description

Dr. Ivanov's research interests include nuclear reactor physics and multi-physics, nuclear core design and safety analysis, nuclear plant simulations, validation and verification of multi-physics calculations, and uncertainty quantification and propagation in modeling.

Publications

Benchmarking the real-time core model for VVER-1000 simulator application on asymmetric core load

Georgieva, E., Dinkov, Y., & Ivanov, K. (2017), Journal of Nuclear Engineering and Radiation Science, 3(3).

OECD/NEA benchmark for time-dependent neutron transport calculations without spatial homogenization

Hou, J., Ivanov, K. N., Boyarinov, V. F., & Fomichenko, P. A. (2017), Nuclear Engineering and Design, 317, 177–189.

Rod internal pressure distribution and uncertainty analysis using FRAPCON

Bratton, R. N., Jessee, M. A., Wieselquist, W. A., & Ivanov, K. N. (2017), Nuclear Technology, 197(1), 47–63.

Advances in the Pennsylvania State University NEM code

Thompson, S. A., & Ivanov, K. N. (2016), Annals of Nuclear Energy, 94, 251–262.

Benchmarking the NEM real-time core model for VVER-1000 simulator application - asymmetric core

Georgieva, E., Dinkov, Y., Ivanov, K., & Stieglitz, R. (2016),

Coupled MCNP6/CTF code: Development, testing, and application

Bennett, A., Avramova, M., & Ivanov, K. (2016), Annals of Nuclear Energy, 96, 1–11.

The IAEA coordinated research programme on HTGR uncertainty analysis: Phase I status and Ex. I-1 prismatic reference results

Bostelmann, F., Strydom, G., Reitsma, F., & Ivanov, K. (2016), Nuclear Engineering and Design, 306, 77–88.

Development of an iterative diffusion-transport method based on MICROX-2 cross section libraries

Hou, J., Choi, H., & Ivanov, K. (2015), Annals of Nuclear Energy, 77, 335–342.

Assessment of MICROX-2 Code with new ENDF/B-VII.0 master library

Hou, J., Choi, H., & Ivanov, K. (2014), Nuclear Technology, 186(3), 305–316 .

Self-shielding models of MICROX-2 code: Review and updates

Hou, J., Choi, H., & Ivanov, K. (2014), Annals of Nuclear Energy, 64, 256–263 .

View all publications via NC State Libraries

Grants

Develop Educational program in VVUQ - Multiphysica

US Dept. of Energy (DOE)(11/29/18 - 9/30/19)

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Develop Educational program in VVUQ - Multiphysica

Sponsor: US Dept. of Energy (DOE)

Start Date: 11/29/18

End Date: 9/30/19

Abstract

The work performed under this subcontract by Drs. Maria Avramova and Kostadin Ivanov will support the development of educational program in Verification, Validation and Uncertainty Quantification (VVUQ) of single- and multi-physics modeling and simulation (M&S) tools in nuclear science and engineering applications. EGMPEBV is focused on benchmarking, validation procedures, development of experimental databases and uncertainty propagation. There is a need for a new subtask on educational aspects/training for VVUQ for nuclear applications. The work performed under this subcontract will also supports activities associated with the Expert Group on Multi-Physics Experimental data, Benchmarks and Validation (EGMPEBV) of the Nuclear Energy Agency (NEA) of the Organization for Economic Cooperation and Development (OECD).

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Multi-physics Modeling of Fast Spectrum Liquid Fuel MSRs, Consortium for Nuclear Power (CNP) Core Project - 1.

Consortium for Nuclear Power (CNP)(7/01/18 - 6/30/19)

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Multi-physics Modeling of Fast Spectrum Liquid Fuel MSRs, Consortium for Nuclear Power (CNP) Core Project - 1.

Sponsor: Consortium for Nuclear Power (CNP)

Start Date: 7/01/18

End Date: 6/30/19

Abstract

The project will model Molten Salt Reactor (MSR) transients. The modeling will utilize tightly coupling of the complete form of P1 approximation for neutron transport equation to a Computational Fluid Dynamics (CFD) solver for fast spectrum liquid fuel MSR applications. We believe that this multi-physics modeling approach provides the right level of accuracy and speed (efficiency) to study the safety characteristics of MSRs.

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Multi-physics platform for safety analysis based on NRC codes Improved estimates of local safety parameters for efficient evaluation of realistic safety margins for real-size reactor core modeling

National Nuclear Regulator(4/01/18 - 3/31/20)

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Multi-physics platform for safety analysis based on NRC codes Improved estimates of local safety parameters for efficient evaluation of realistic safety margins for real-size reactor core modeling

Sponsor: National Nuclear Regulator

Start Date: 4/01/18

End Date: 3/31/20

Abstract

This project will establish a multi-physics platform for safety analysis based on NRC codes and capable of providing improved estimates of local safety parameters for efficient evaluation of realistic safety margins for real-size reactor core modeling.

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Nuclear Energy Knowledge and Validation Center (NEKVac)

US Dept. of Energy (DOE)(12/19/16 - 9/30/17)

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Nuclear Energy Knowledge and Validation Center (NEKVac)

Sponsor: US Dept. of Energy (DOE)

Start Date: 12/19/16

End Date: 9/30/17

Abstract

The Nuclear Energy Knowledge and Validation Center (NEKVaC) is a new initiative by the Department of Energy (DOE) and Idaho National Laboratory to coordinate and focus the resources and expertise that exist with the DOE Complex toward solving issues in the validation of codes used for modern nuclear plant and fuel cycle analysis. In time, code owners, users, and developers will view the Center as a partner and essential resource for acquiring the best practices and latest techniques for validating codes, for guidance in planning and executing experiments, for facilitating access to, and maximizing the usefulness of, existing data, and for preserving knowledge for continual use by nuclear professionals and organizations for their own validation needs. The scope of the Center covers many inter related activities, which will need to be cultivated carefully in the near term and managed properly once the Center is fully functional.

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Faculty Development Program in Nuclear Engineering at North Carolina State University, 2017

US Nuclear Regulatory Commission(6/30/17 - 6/29/20)

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Faculty Development Program in Nuclear Engineering at North Carolina State University, 2017

Sponsor: US Nuclear Regulatory Commission

Start Date: 6/30/17

End Date: 6/29/20

Abstract

NRC faculty development grants previously awarded to the Department of Nuclear Engineering at North Carolina State University (NCSU) have been extremely beneficial to the development and success of our tenure-track faculty to advance in their academic careers. We hired a new faculty in the area of nuclear materials and we are recruiting and interviewing new entry-level faculty in one of the respective areas of dosimetry and nuclear assay, fission power reactors, thermal hydraulics, and related subjects. The NRC faculty development program will help us supporting the newly hired faculty and the r4ecruiting of new faculty by encouraging recently graduated PhDs of the highest caliber to apply to our program. Upon hiring, and with the NRC award plus what we provide as a startup package, the hired junior faculty will be supported and helped to establish their academic career with the help of the senior faculty mentorship. A measure of the NRC faculty development award will be realized when the tenure-track faculty successfully advances towards tenure and promotion to higher ranks, and earning a reputation within the nuclear engineering institutions. For our department of nuclear engineering, it is a great benefit to hire top talent young faculty in the open positions and to retain recently hired tenure-track faculty with our expansion in all nuclear engineering main thrust research areas.

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Joint Faculty Appointment Between Oak Ridge National Laboratory (ORNL) and NC State University (NCSU) for Dr. David Kropaczek 2016-2017 (FY17).

US Dept. of Energy (DOE)(7/01/16 - 8/05/18)

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Joint Faculty Appointment Between Oak Ridge National Laboratory (ORNL) and NC State University (NCSU) for Dr. David Kropaczek 2016-2017 (FY17).

Sponsor: US Dept. of Energy (DOE)

Start Date: 7/01/16

End Date: 8/05/18

Abstract

Joint appointment as Dr. Kropaczek is considered NCSU employee with NCSU as the assigning party and ORNL CASL as the receiving party pursuant to Joint Faculty Agreement NO JFA-2001-2

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North Carolina State University’s Graduate Fellowship in Nuclear Engineering (NCSU–GFINE) - 2016

US Nuclear Regulatory Commission(7/01/16 - 6/30/20)

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North Carolina State University’s Graduate Fellowship in Nuclear Engineering (NCSU–GFINE) - 2016

Sponsor: US Nuclear Regulatory Commission

Start Date: 7/01/16

End Date: 6/30/20

Abstract

This proposal is a request for financial support for 2 graduate students in nuclear engineering through the North Carolina State University’s Graduate Fellowship in Nuclear Engineering (NCSU–GFINE) program that helps to develop a highly talented and competent workforce with post-baccalaureate education capable of leading the nation’s charge to reinvigorate its nuclear industry. Every attempt will be made during the recruitment and selection processes to ensure that the sponsored students reflect the diverse groups that make up our nation’s populace. Moreover, the high academic standards inherent to NC State’s Department of Nuclear Engineering and the proposed selection formula will ensure the highest caliber of the sponsored fellows. These individuals will shepherd the design, construction, operation, and regulation of new and innovative nuclear facilities, while maintaining the safety and security of processes for the handling of requisite nuclear materials in the coming decades, a period crucial for the revamping of an industry that has fallen to neglect. Upon graduation the sponsored fellows will be contractually required to complete nuclear-related employment at the rate of six months per year of NCSU–GFINE sponsorship. The commitment by NCSU’s Department of Nuclear Engineering and College of Engineering to the success of NCSU–GFINE is evidenced by a cost-sharing contribution.

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Research Activities in the field of development and coupling COBRA-TF code version for research and power reactors.

South African Nuclear Energy Corporation SOC Ltd (NESCA)(1/01/16 - 5/31/19)

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Research Activities in the field of development and coupling COBRA-TF code version for research and power reactors.

Sponsor: South African Nuclear Energy Corporation SOC Ltd (NESCA)

Start Date: 1/01/16

End Date: 5/31/19

Abstract

The Necsa has granted funds to to carry out research activities in the field of development and coupling COBRA-TF code version for research and power reactors. This grant will provide general support, guidance and training with regard to the establishment of an independent power reactor calculation capability at Necsa. The NCSU will continue to develop the COBRA-TF code system and shall provide Necsa with updates as available. This agreement then enables a cost free, non-commercial use of the multi-user license of COBRA-TF at Necsa.

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Participation in the MPEBV efforts with the NEA

US Dept. of Energy (DOE)(2/10/16 - 9/30/19)

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Participation in the MPEBV efforts with the NEA

Sponsor: US Dept. of Energy (DOE)

Start Date: 2/10/16

End Date: 9/30/19

Abstract

The work performed under this subcontract supports activities associated with the Expert Group on Multi-physics Experimental Data, Benchmarks and Validation (MPEBV) of the Nuclear Energy Agency (NEA) of the Organization for Economic Cooperation and Development (OECD). The work performed under this subcontract by Drs. Maria Avramova and Kostadin Ivanov will support the development of methodologies and guidelines for traditional and novel methods for validation of multi-physics modeling and simulation (M&S) tools. Drs. Avramova and Ivanov will be responsible for contributing to the NEA reports on the current status and expected needs for validation of multi-physics M&S tools as well as contributing to the NEA report on the frameworks for assessing the rigor and completeness of M&S tools for predictive applications. In addition, Drs. Avramova and Ivanov will lead the U.S. efforts to develop a work plan in cooperation with representative from the Russian Federation for evaluating the feasibility of application of validation methodologies to specific VVER reactor transients.

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NCSU Participation in IAEA Coordinated Research Program on HTGR Uncertainty Analysis in Modeling

US Dept. of Energy (DOE)(12/01/15 - 9/30/18)

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NCSU Participation in IAEA Coordinated Research Program on HTGR Uncertainty Analysis in Modeling

Sponsor: US Dept. of Energy (DOE)

Start Date: 12/01/15

End Date: 9/30/18

Abstract

The Technical Working Group on Gas Cooled Reactors (TWG GCR) recommended that the proposed International Atomic Energy Agency (IAEA) Coordinated Research Program (CRP) on the High Temperature Gas Cooled Reactor (HTGR) Uncertainty Analysis in Modeling (UAM) be implemented in 2009. This CRP is dedicated to the uncertainty quantification of HTGR simulation and will assess the state-of-the-art in current HTGR simulation capabilities. The proposed technical approach is to establish and utilize a benchmark for uncertainty analysis in best-estimate coupled HTGR modelling and analysis, using as a basis a series of well-defined problems with complete sets of input specifications and as far as possible reference experimental data. The prismatic Modular High Temperature Gas Cooled Reactor (MHTGR-350) has been selected as reference reactor for the prismatic benchmark problem. The principal idea is to subdivide the coupled system calculation into several steps, each of which can contribute to the total uncertainty and to identify input, output, and assumptions for each step. The resulting uncertainty in each step will be calculated by taking into account all sources of uncertainties including propagating the related uncertainties from previous steps. The four phases are as follows: • Phase I (Local Standalone Modelling) • Phase II (Global Standalone Modelling) • Phase III (Design Calculations) • Phase IV (Safety Calculations)

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