Education

Research Description

Dr. Avramova's research areas include reactor thermal-hydraulics; core design; transient and safety analysis; multi-physics and multi-scale simulations; verification and validation; and uncertainty and sensitivity analysis.

Publications

BWR core thermal-hydraulic uncertainty and sensitivity analysis with improved bypass modeling features

Ziyad, D., Abarca, A., & Avramova, M. (2025), NUCLEAR ENGINEERING AND DESIGN, 435. https://doi.org/10.1016/j.nucengdes.2025.113951

Development of Serpent/CTF External Coupling for the OECD/NEA TVA-WB1 Benchmark Activities

Albagami, T., Rouxelin, P., Abarca, A., Palmtag, S., Avramova, M., & Ivanov, K. (2025, April 27), NUCLEAR SCIENCE AND ENGINEERING, Vol. 4. https://doi.org/10.1080/00295639.2025.2475415

Sensitivity and uncertainty analysis in pebble-bed reactors: A study using the High-Temperature Code Package (HCP)

Yaseen, M., Sadek, A., Osman, W., Altahhan, M., Wu, X., Avramova, M., & Ivanov, K. (2025), ANNALS OF NUCLEAR ENERGY, 219. https://doi.org/10.1016/j.anucene.2025.111428

Uncertainty Quantification Framework for High-Temperature Gas-Cooled Reactors Using VSOP and DAKOTA

Delipei, G. K., Altahhan, M., Rouxelin, P., Sen, S., George, N., Avramova, M., & Ivanov, K. (2025, May 15), NUCLEAR SCIENCE AND ENGINEERING, Vol. 5. https://doi.org/10.1080/00295639.2025.2486901

A Framework for Multi-Physics Modeling, Design Optimization and Uncertainty Quantification of Fast-Spectrum Liquid-Fueled Molten-Salt Reactors

Holler, D., Bhaskar, S., Delipei, G., Avramova, M., & Ivanov, K. (2024), APPLIED SCIENCES-BASEL, 14(17). https://doi.org/10.3390/app14177615

Fuel performance code to code comparative analysis for the OECD/NEA MPCMIV benchmark

Faure, Q., Delipei, G., Scolaro, A., Avramova, M., & Ivanov, K. (2024), NUCLEAR ENGINEERING AND DESIGN, 430. https://doi.org/10.1016/j.nucengdes.2024.113685

Investigation of Transients with Serpent using the OECD/NEA C5G7-TD Benchmark

Fernandes, A. C. A. A., Rouxelin, P., Ivanov, K., & Avramova, M. (2024), JOINT INTERNATIONAL CONFERENCE ON SUPERCOMPUTING IN NUCLEAR APPLICATIONS + MONTE CARLO, SNA + MC 2024, Vol. 302. https://doi.org/10.1051/epjconf/202430212004

Challenge for the validation of high-fidelity multi-physics LWR modeling and simulation: Development of new experiments in research reactors

Vaglio-Gaudard, C., Destouches, C., Hawari, A., Avramova, M., Ivanov, K., Valentine, T., … Hudelot, J.-P. (2023), Frontiers in Energy Research, 11. https://doi.org/10.3389/fenrg.2023.1110979

Development of an efficient and improved core thermal-hydraulics predictive capability for fast reactors: Summary of research and development activities at the North Carolina state University

Takasugi, C., Aly, A., Holler, D., Abarca, A., Beeler, B., Avramova, M., & Ivanov, K. (2023), Nuclear Engineering and Design, 412, 112474. https://doi.org/10.1016/j.nucengdes.2023.112474

Fuel performance uncertainty quantification and sensitivity analysis in the presence of epistemic and aleatoric sources of uncertainties

Faure, Q., Delipei, G., Petruzzi, A., Avramova, M., & Ivanov, K. (2023), Frontiers in Energy Research, 11. https://doi.org/10.3389/fenrg.2023.1112978

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Grants

Membership in Consortium for Nuclear Power (CNP), Full Member

Electric Power Research Institute, Inc.(7/01/21 - 6/30/27)

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Membership in Consortium for Nuclear Power (CNP), Full Member

Sponsor: Electric Power Research Institute, Inc.

Start Date: 7/01/21

End Date: 6/30/27

Abstract

Full Membership with CNP

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Membership in Consortium for Nuclear Power (CNP), Full Member

Framatome(2/01/19 - 6/30/27)

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Membership in Consortium for Nuclear Power (CNP), Full Member

Sponsor: Framatome

Start Date: 2/01/19

End Date: 6/30/27

Abstract

Full Membership with CNP and Framatome

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Membership in Consortium for Nuclear Power (CNP) - Affiliate Member

Tractebel Engineering S.A.(7/01/18 - 6/30/27)

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Membership in Consortium for Nuclear Power (CNP) - Affiliate Member

Sponsor: Tractebel Engineering S.A.

Start Date: 7/01/18

End Date: 6/30/27

Abstract

Affiliate Membership with CNP

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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 - 12/31/25)

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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: 12/31/25

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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Integral Benchmark Evaluation of Zero-Power Tests and Multi-Cycle Depletion Experimental Data of TVA WB1

US Dept. of Energy (DOE)(10/01/21 - 7/31/25)

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Integral Benchmark Evaluation of Zero-Power Tests and Multi-Cycle Depletion Experimental Data of TVA WB1

Sponsor: US Dept. of Energy (DOE)

Start Date: 10/01/21

End Date: 7/31/25

Abstract

This project proposes to develop an integral benchmark evaluation from available experimental data for zero-power tests and multi-cycle depletion for consistent and comprehensive validation of both novel high-fidelity and traditional multi-physics tools. The benchmark evaluation will be based on design, operational, and measured data from the Pressurized Water Reactor (PWR) Watts Bar Unit 1 (WB1) released by Tennessee Valley Authority (TVA). Initially this data was released for a series of benchmark progression problems developed by the Consortium for the Advanced Simulation of Light Water Reactors (CASL), a U.S. Department of Energy (DOE) Energy Innovation Hub for Reactor Modeling and Simulation (M&S) focused on developing and applying the Virtual Environment for Reactor Applications (VERA) to improve the operation and safety of Light Water Reactors (LWRs).

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Membership in Consortium for Nuclear Power (CNP), Full Member

General Electric (GE) -Hitachi(7/01/22 - 6/30/25)

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Membership in Consortium for Nuclear Power (CNP), Full Member

Sponsor: General Electric (GE) -Hitachi

Start Date: 7/01/22

End Date: 6/30/25

Abstract

CNP Full Member

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Membership in Consortium for Nuclear Power (CNP), Affiliate Member

Kernkraftwerk Leibstadt AG(7/01/22 - 6/30/25)

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Membership in Consortium for Nuclear Power (CNP), Affiliate Member

Sponsor: Kernkraftwerk Leibstadt AG

Start Date: 7/01/22

End Date: 6/30/25

Abstract

Development and Validation Support for Coupling of KKL TRACE-S3K Model Order for Membership period, from July 2022 - June 2023

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Membership in Consortium for Nuclear Power (CNP), Full Member

Duke Energy Carolinas, LLC(7/01/22 - 6/30/25)

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Membership in Consortium for Nuclear Power (CNP), Full Member

Sponsor: Duke Energy Carolinas, LLC

Start Date: 7/01/22

End Date: 6/30/25

Abstract

CNP Membership

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BWXT Small Mobile Nuclear Reactor (SMNR) Program Phase 2 for North Carolina State University (NCSU)

US Dept. of Defense (DOD)(1/12/23 - 10/31/24)

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BWXT Small Mobile Nuclear Reactor (SMNR) Program Phase 2 for North Carolina State University (NCSU)

Sponsor: US Dept. of Defense (DOD)

Start Date: 1/12/23

End Date: 10/31/24

Abstract

Input to the Preliminary PIRT report: meeting participation, design familiarization, identification, description and ranking of candidate limiting design-basis events with respect to phenomena, assessment and ranking of state of knowledge of identified phenomena

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Benchmark Evaluation of Transient Multi-Physics Experimental Data for Pellet Cladding Mechanical Interactions; CFA-20-19590

US Dept. of Energy (DOE)(10/01/20 - 9/30/24)

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Benchmark Evaluation of Transient Multi-Physics Experimental Data for Pellet Cladding Mechanical Interactions; CFA-20-19590

Sponsor: US Dept. of Energy (DOE)

Start Date: 10/01/20

End Date: 9/30/24

Abstract

The goal of the proposed project is to develop an integral benchmark evaluation based on available experimental data from cold ramp tests performed at the Studsvik testing R2 reactor. Such transient multi-physics benchmark evaluations are needed to support the U.S. DOE Nuclear Energy (NE) such as Fuel Cycle Technologies (FCT), LWR Sustainability (LWRS), and Advanced Modeling and Simulation (AMS) programs for validation of the NEAMS ToolKit and the VERA suite. Evaluation of transient multi-physics experimental data for LWR systems is a growing area of interest for U.S. DOE. Analyses of reactivity-initiated accidents such as design basis accidents as well as the slower and less severe anticipated operating occurrences (AOOs) are important in determining the overall safety of the current fleet and future nuclear power plants. Industry challenge problems, as the pellet cladding interaction (PCI) and the pellet cladding mechanical interaction (PCMI), are associated with those events. PCI and PCMI are based on multi-physics and multi-scale phenomena requiring accurate and realistic modeling and simulation. Three-dimensional fuel performance models coupled with reactor physics and thermal-hydraulics models are needed to assess the complex coupled physics and irregular geometries responsible for PCI/PCMI fuel failures. At present time, there is a need for adequate high-quality experimental data for PCI/PCMI industry challenge problems to properly validate both the existing multi-physics tools and as well as the high-fidelity multi-physics code systems being developed. The proposed project will address this need by evaluating test reactor data from controlled experimentation. The selected cold ramp tests were performed in 2005 and were experimental simulations of an uncontrolled withdrawal of a control rod group in a cold critical LWR which is a reactivity transient representative of AOOs. These special cold ramp tests were selected to: (1) develop a case problem based on measurements that involve two or more physical phenomena; and (2) investigate PCMI phenomenon in fuel rods. The selected dynamic/transient tests are multi-physics by nature: involve transient changes and interactions between reactor physics, thermal-hydraulics, and fuel performance. Multi-physics benchmark specifications will be developed to provide the data necessary to construct calculation models. The IRPhEP guidelines will be extended to make the evaluation process applicable for multi-physics transients. All available R2 reactor information, related to the initial conditions and transient tests, will be utilized. The information will constitute the Benchmark Experiment Data. This data will be subjected to Benchmark Evaluation Process. Based on the lessons learnt during the preparation of the benchmark specifications and its execution, a proposal for developing a multi-physics and transient evaluation protocol will be prepared using similar review pathway and similar evaluation format as the one established in IRPhEP: collecting benchmark experimental data, follow-up benchmark evaluation process, and peer review.

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