Works (64)

Updated: March 27th, 2025 13:44

2025 journal article

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

NUCLEAR ENGINEERING AND DESIGN, 435.

By: D. Ziyad, A. Abarca & M. Avramova*

author keywords: BWR bypass modeling; Uncertainty and sensitivity analysis; Subchannel analysis; CTF
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics; Probabilistic and Robust Engineering Design
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7. Affordable and Clean Energy (OpenAlex)
Sources: Web Of Science, NC State University Libraries
Added: March 10, 2025

2024 journal article

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

APPLIED SCIENCES-BASEL, 14(17).

By: D. Holler n, S. Bhaskar n, G. Delipei n, M. Avramova n & K. Ivanov n

author keywords: uncertainty quantification; sensitivity analysis; CFD; GeN-Foam; multi-physics
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Materials and Properties; Nuclear Engineering Thermal-Hydraulics
Sources: Web Of Science, ORCID, NC State University Libraries
Added: September 1, 2024

2024 journal article

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

NUCLEAR ENGINEERING AND DESIGN, 430.

By: Q. Faure*, G. Delipei, A. Scolaro, M. Avramova* & K. Ivanov*

author keywords: Fuel performance; FAST; OFFBEAT; BISON; Pellet Cladding Mechanical Interaction (PCMI)
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Materials and Properties; Heat transfer and supercritical fluids
Sources: Web Of Science, NC State University Libraries
Added: December 2, 2024

2024 article

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

JOINT INTERNATIONAL CONFERENCE ON SUPERCOMPUTING IN NUCLEAR APPLICATIONS + MONTE CARLO, SNA + MC 2024, Vol. 302.

By: A. Fernandes, P. Rouxelin*, K. Ivanov* & M. Avramova*

topics (OpenAlex): Nuclear Materials and Properties; Advanced Neural Network Applications; Nuclear reactor physics and engineering
Sources: Web Of Science, NC State University Libraries
Added: February 10, 2025

2023 journal article

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

Frontiers in Energy Research, 11.

author keywords: multi-physics; high-fidelity; coupling; validation; experiment; research reactors; reactivity feedback effects
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics; Nuclear Materials and Properties
Sources: Web Of Science, NC State University Libraries, Crossref
Added: March 6, 2023

2023 journal article

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

Nuclear Engineering and Design, 412, 112474.

By: C. Takasugi n, A. Aly n, D. Holler n, A. Abarca n, B. Beeler n, M. Avramova n, K. Ivanov n

author keywords: CTF; Sodium fast reactors; Multi-physics; Hi2Lo
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics; Nuclear Materials and Properties
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Sources: Web Of Science, NC State University Libraries, Crossref
Added: August 21, 2023

2023 journal article

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

Frontiers in Energy Research, 11.

By: Q. Faure n, G. Delipei n, A. Petruzzi, M. Avramova n & K. Ivanov n

author keywords: fuel performance; uncertainty quantification (UQ); sensitivity analysis (SA); aleatoric uncertainty; epistemic uncertainty; pellet cladding mechanical interaction (PCMI)
topics (OpenAlex): Probabilistic and Robust Engineering Design; Nuclear reactor physics and engineering; Nuclear Materials and Properties
Sources: Web Of Science, NC State University Libraries, Crossref
Added: April 17, 2023

2023 journal article

Preservation of kinetics parameters generated by Monte Carlo calculations in two-step deterministic calculations

EPJ Nuclear Sciences & Technologies, 9, 15.

topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Materials and Properties; Nuclear Physics and Applications
TL;DR: Study of the preservation of bilinearly-weighted quantities in the Serpent–Griffin calculation procedure finds sensitivities to multigroup energy grid selection and regional application of SPH equivalence were demonstrated to be reduced through the use of a transport method together with a finer energy grid. (via Semantic Scholar)
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7. Affordable and Clean Energy (OpenAlex)
Sources: Web Of Science, NC State University Libraries, Crossref
Added: March 27, 2023

2022 journal article

Ab initio molecular dynamics investigation of gamma-(U,Zr) structural and thermal properties as a function of temperature and composition

JOURNAL OF NUCLEAR MATERIALS, 561.

By: A. Aly n, B. Beeler n & M. Avramova n

author keywords: AIMD; DFT; Nuclear fuel element; Metallic Fuel; Uranium; U-Zr
topics (OpenAlex): Nuclear Materials and Properties; Thermodynamic and Structural Properties of Metals and Alloys; Rare-earth and actinide compounds
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7. Affordable and Clean Energy (Web of Science; OpenAlex)
Sources: Web Of Science, NC State University Libraries
Added: May 23, 2022

2022 journal article

CTF-PARCS Core Multi-Physics Computational Framework for Efficient LWR Steady-State, Depletion and Transient Uncertainty Quantification

Energies, 15(14), 5226.

By: G. Delipei n, P. Rouxelin n, A. Abarca n, J. Hou n, M. Avramova n & K. Ivanov n

author keywords: multi-physics; CTF; PARCS; LWR; uncertainty quantification
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics; Nuclear Materials and Properties
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6. Clean Water and Sanitation (OpenAlex)
Sources: Web Of Science, ORCID, NC State University Libraries, Crossref
Added: July 20, 2022

2022 journal article

CTF: A modernized, production-level, thermal hydraulic solver for the solution of industry-relevant challenge problems in pressurized water reactors

NUCLEAR ENGINEERING AND DESIGN, 397.

By: R. Salko*, A. Wysocki*, T. Blyth*, A. Toptan*, J. Hu*, V. Kumar*, C. Dances*, W. Dawn n ...

author keywords: Subchannel; LWR; CTF; VERA
topics (OpenAlex): Nuclear Engineering Thermal-Hydraulics; Nuclear reactor physics and engineering; Nuclear Materials and Properties
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13. Climate Action (Web of Science)
Sources: Web Of Science, NC State University Libraries
Added: September 26, 2022

2022 article proceedings

Development of a High-Fidelity Multi-Physics Coupling Between MCNP6.2 and CTF4.0 for VVER Applications

By: Y. Kutlu, P. Rouxelin, M. Avramova* & K. Ivanov

topics (OpenAlex): Magnetic confinement fusion research; Nuclear reactor physics and engineering; Laser-Plasma Interactions and Diagnostics
UN Sustainable Development Goals Color Wheel
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7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: March 24, 2025

2022 journal article

Digital-twin-based improvements to diagnosis, prognosis, strategy assessment, and discrepancy checking in a nearly autonomous management and control system

ANNALS OF NUCLEAR ENERGY, 166.

By: L. Lin n, P. Athe n, P. Rouxelin n, M. Avramova n, A. Gupta n, R. Youngblood*, J. Lane*, N. Dinh n

Contributors: L. Lin n, P. Athe n, P. Rouxelin n, M. Avramova n, A. Gupta n, R. Youngblood*, J. Lane*, N. Dinh n

author keywords: autonomous control; digital twin; diagnosis; prognosis
topics (OpenAlex): Fault Detection and Control Systems; Nuclear Engineering Thermal-Hydraulics; Nuclear reactor physics and engineering
TL;DR: This study refines a NAMAC system for making reasonable recommendations during complex loss-of-flow scenarios with a validated Experimental Breeder Reactor II simulator, digital twins improved by machine-learning algorithms, a multi-attribute decision-making scheme, and a discrepancy checker for identifying unexpected recommendation effects. (via Semantic Scholar)
Sources: Web Of Science, NC State University Libraries, Crossref, ORCID
Added: November 1, 2021

2022 journal article

Extending a low-order inhomogeneous adjoint equations model to a higher-order model with verification on integral applications

Annals of Nuclear Energy, 177, 109277.

By: M. Altahhan n, R. van Geemert, M. Avramova* & K. Ivanov*

author keywords: Nodal Expansion Method (NEM); Adjoint Lagrange Multiplier; Axial Offset (AO); Perturbation analysis; Sensitivity analysis; IAEA
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Materials and Properties; Advancements in Semiconductor Devices and Circuit Design
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Sources: Web Of Science, NC State University Libraries, Crossref
Added: May 30, 2023

2022 journal article

Investigation of ?-(U, Zr) structural properties and its interfacial properties with liquid sodium using ab initio molecular dynamics

JOURNAL OF NUCLEAR MATERIALS, 567.

By: A. Aly n, B. Beeler n & M. Avramova n

author keywords: Uranium; Metallic fuel; Interfacial energy; Elastic constants; Sodium bond; Sound velocity
topics (OpenAlex): Nuclear Materials and Properties; Nuclear reactor physics and engineering; Fusion materials and technologies
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7. Affordable and Clean Energy (Web of Science; OpenAlex)
Sources: Web Of Science, ORCID, NC State University Libraries
Added: June 4, 2022

2022 article proceedings

Machine Learning-Based Prediction of Departure from Nucleate Boiling Power for the PSBT Benchmark

By: C. Godbole, G. Delipei, X. Wu, M. Avramova* & U. Rohatgi

topics (OpenAlex): Nuclear reactor physics and engineering
Sources: Crossref, NC State University Libraries
Added: March 24, 2025

2022 article proceedings

OECD/NEA MPCMIV Benchmark -- Preliminary Fuel Performance Results

By: Q. Faure, G. Delipei, M. Avramova* & K. Ivanov*

topics (OpenAlex): Catalytic Processes in Materials Science
Sources: Crossref, NC State University Libraries
Added: March 24, 2025

2022 journal article

Off-line vs. semi-implicit TH-TH coupling schemes: A BEPU comparison

ANNALS OF NUCLEAR ENERGY, 178.

By: M. Casamor*, M. Avramova n, F. Reventós* & J. Freixa*

author keywords: PWR; Coupling; BEPU; DNBR
topics (OpenAlex): Nuclear Engineering Thermal-Hydraulics; Nuclear reactor physics and engineering; Computational Fluid Dynamics and Aerodynamics
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Sources: Web Of Science, NC State University Libraries, Crossref
Added: October 2, 2023

2022 article proceedings

Phase I Specifications and Preliminary Sensitivity Analyses of the OECD-NRC Liquid Metal Fast Reactor Core Thermal-Hydraulics Benchmark

By: D. Holler, M. Avramova*, C. Takasugi, R. Vaghetto & Y. Hassan

topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics; Fusion materials and technologies
Sources: Crossref, NC State University Libraries
Added: March 24, 2025

2022 journal article

Propagation of VHTRC manufacturing uncertainties with RAVEN/PHISICS

Annals of Nuclear Energy, 165, 108667.

By: P. Rouxelin n, A. Alfonsi*, G. Strydom*, M. Avramova n & K. Ivanov n

author keywords: PHISICS; RAVEN; VHTRC; Manufacturing Uncertainties; Monte Carlo Sampling
topics (OpenAlex): Nuclear reactor physics and engineering; Graphite, nuclear technology, radiation studies; Nuclear Materials and Properties
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7. Affordable and Clean Energy (OpenAlex)
Sources: Web Of Science, NC State University Libraries, Crossref
Added: November 8, 2021

2022 article proceedings

Quantification of the Importance of the Modeling Fidelity in the Best Estimate Plus Uncertainty Analysis

By: G. Delipei, A. Abarca, P. Rouxelin, M. Avramova* & K. Ivanov*

topics (OpenAlex): Risk and Safety Analysis; Environmental Policies and Emissions; Forecasting Techniques and Applications
Sources: Crossref, NC State University Libraries
Added: March 24, 2025

2022 article proceedings

Status of the OECD/NEA Watts Bar Unit 1 Benchmark and Calculations of Local Reactor Core Power Data of the Zero Power Physics Tests

By: T. Albagami, P. Rouxelin, S. Palmtag, M. Avramova* & K. Ivanov

topics (OpenAlex): Graphite, nuclear technology, radiation studies; Nuclear reactor physics and engineering; Nuclear and radioactivity studies
UN Sustainable Development Goals Color Wheel
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: March 24, 2025

2022 article proceedings

julia for Enhancing Nuclear Engineering Simulations (JENES): Introduction to the JENES Project and Platform

By: M. Altahhan, G. Delipei, D. Holler, J. Hou, M. Avramova* & K. Ivanov*

topics (OpenAlex): Nuclear and radioactivity studies; Nuclear reactor physics and engineering
Sources: Crossref, NC State University Libraries
Added: March 24, 2025

2021 journal article

Development and assessment of a nearly autonomous management and control system for advanced reactors

Annals of Nuclear Energy, 150.

Contributors: L. Lin n, P. Athe n, P. Rouxelin n, M. Avramova n, A. Gupta n, R. Youngblood*, J. Lane*, N. Dinh n

author keywords: Autonomous control; Digital twin; Diagnosis; Prognosis
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics; Graphite, nuclear technology, radiation studies
TL;DR: A baseline NAMAC is implemented for operating a simulator of the Experimental Breeder Reactor II during a single loss of flow accident, and can provide reasonable recommendations that prevent the peak fuel centerline temperature from exceeding a safety criterion. (via Semantic Scholar)
Sources: Crossref, NC State University Libraries, ORCID
Added: October 19, 2020

2021 journal article

Development and verification of a higher-order mathematical adjoint nodal diffusion solver

Annals of Nuclear Energy, 163, 108548.

By: M. Altahhan n, R. van Geemert*, M. Avramova n & K. Ivanov n

author keywords: Nodal Expansion Method (NEM); Lagrange multiplier; Adjoint; Diffusion equation; Verification; Perturbation analysis; Sensitivity analysis; IAEA-3D benchmark
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Physics and Applications; Nuclear Materials and Properties
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Sources: Web Of Science, NC State University Libraries, Crossref
Added: September 7, 2021

2021 journal article

Innovations in Multi-Physics Methods Development, Validation, and Uncertainty Quantification

Journal of Nuclear Engineering, 2(1), 44–56.

By: M. Avramova n, A. Abarca n, J. Hou n & K. Ivanov n

topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics; Probabilistic and Robust Engineering Design
Sources: ORCID, Crossref, NC State University Libraries
Added: March 8, 2021

2021 journal article

Summary of comparative analysis and conclusions from OECD/NEA LWR-UAM benchmark Phase I

Nuclear Engineering and Design, 384, 111474.

By: G. Delipei n, J. Hou n, M. Avramova n, P. Rouxelin n & K. Ivanov n

author keywords: LWR; Uncertainty analysis; Benchmark; Neutronics; Summary
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics; Nuclear Materials and Properties
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6. Clean Water and Sanitation (OpenAlex)
Sources: Web Of Science, NC State University Libraries, Crossref, ORCID
Added: October 1, 2021

2020 journal article

Best-Estimate Plus Uncertainty Framework for Multiscale, Multiphysics Light Water Reactor Core Analysis

Science and Technology of Nuclear Installations, 2020, 1–18.

By: J. Hou n, M. Avramova n & K. Ivanov n

topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics; Nuclear Materials and Properties
Sources: Crossref, NC State University Libraries, ORCID
Added: August 1, 2020

2020 journal article

Developments in thermal-hydraulic sub-channel modeling for whole core multi-physics simulations

Avramova, M. (2020, March). NUCLEAR ENGINEERING AND DESIGN, Vol. 358.

By: M. Avramova n

author keywords: Sub-channel modeling; Whole core multi-physics simulations; Physics-informed data-driven modeling
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics; Nuclear Materials and Properties
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Sources: Web Of Science, NC State University Libraries, Crossref
Added: February 10, 2020

2020 journal article

Modular high temperature gas reactor core modeling with RELAP5-3D/PHISICS – Optimization schemes for load following

Modular high temperature gas reactor core modeling with RELAP5-3D/ PHISICS ? Optimization schemes for load following. NUCLEAR ENGINEERING AND DESIGN, 362.

By: P. Balestra n, K. Henry n, C. Carlyon n, C. English n, J. Myer n, M. Avramova n, A. Epiney*, G. Strydom*

topics (OpenAlex): Nuclear reactor physics and engineering; Fault Detection and Control Systems; Nuclear Materials and Properties
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Sources: Web Of Science, NC State University Libraries, Crossref
Added: July 6, 2020

2020 journal article

Preliminary design and analysis of Liquid Fuel Molten Salt Reactor using multi-physics code GeN-Foam

Nuclear Engineering and Design, 369, 110826.

By: M. Altahhan n, S. Bhaskar n, D. Ziyad n, P. Balestra n, C. Fiorina*, J. Hou n, N. Smith*, M. Avramova n

author keywords: Molten Salt Reactor; CFD; Multiphysics; GeN-Foam; OpenFOAM; Nuclear energy; Liquid fuel
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Materials and Properties; Nuclear and radioactivity studies
Source: ORCID
Added: November 30, 2020

2019 journal article

A new fuel modeling capability, CTFFuel, with a case study on the fuel thermal conductivity degradation

NUCLEAR ENGINEERING AND DESIGN, 341, 248–258.

By: A. Toptan n, R. Salko*, M. Avramova n, K. Clarno* & D. Kropaczek n

author keywords: CTFFuel; Thermal conductivity degradation; CTF; SQA; Verification
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Materials and Properties; Nuclear Engineering Thermal-Hydraulics
UN Sustainable Development Goals Color Wheel
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7. Affordable and Clean Energy (OpenAlex)
Sources: Web Of Science, ORCID, NC State University Libraries, Crossref
Added: December 31, 2018

2019 journal article

A surrogate model based on sparse grid interpolation for boiling water reactor subchannel void distribution

ANNALS OF NUCLEAR ENERGY, 131, 51–62.

By: A. Bennett*, N. Martin* & M. Avramova n

author keywords: Sparse grids; Void distribution; Local void model; F-COBRA-TF; ATRIUM 10; APOLLO2-A
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Materials and Properties; Nuclear and radioactivity studies
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6. Clean Water and Sanitation (OpenAlex)
Sources: Web Of Science, NC State University Libraries, Crossref
Added: July 22, 2019

2019 journal article

CTF-R: A novel residual-based thermal hydraulic solver

NUCLEAR ENGINEERING AND DESIGN, 348, 37–45.

By: N. Porter*, V. Mousseau* & M. Avramova n

author keywords: Subchannel analysis; Residual; CTF; COBRA
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics; Fluid Dynamics Simulations and Interactions
TL;DR: This work develops a novel residual-based code, CTF-R, which is not limited by the strict computational limitations of the early 1980’s, and can therefore be designed such that it is inherently flexible and easy to use. (via Semantic Scholar)
Sources: Web Of Science, NC State University Libraries, Crossref
Added: June 4, 2019

2019 journal article

Gap conductance modeling I: Theoretical considerations for single- and multi-component gases in curvilinear coordinates

NUCLEAR ENGINEERING AND DESIGN, 353.

By: A. Toptan n, D. Kropaczek n & M. Avramova n

author keywords: Gap conductance; Temperature jump distance; Thermal accommodation coefficient; Static load; Mixture
topics (OpenAlex): Nuclear Materials and Properties; Nuclear Engineering Thermal-Hydraulics; Granular flow and fluidized beds
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7. Affordable and Clean Energy (OpenAlex)
Sources: Web Of Science, ORCID, NC State University Libraries, Crossref
Added: October 21, 2019

2019 journal article

Gap conductance modeling II: Optimized model for UO2-Zircaloy interfaces

NUCLEAR ENGINEERING AND DESIGN, 355.

By: A. Toptan n, D. Kropaczek n & M. Avramova n

author keywords: Gap conductance; Continuum; Ross-Stoute; Nuclear fuel performance; Uncertainty; Doppler temperature
topics (OpenAlex): Nuclear Materials and Properties; Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics
UN Sustainable Development Goals Color Wheel
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6. Clean Water and Sanitation (OpenAlex)
Sources: Web Of Science, ORCID, NC State University Libraries, Crossref
Added: November 18, 2019

2019 journal article

On the validity of the dilute gas assumption for gap conductance calculations in nuclear fuel performance codes

NUCLEAR ENGINEERING AND DESIGN, 350, 1–8.

By: A. Toptan n, D. Kropaczek n & M. Avramova n

author keywords: Fill gas thermal conductivity; Gap conductance; Fuel performance; Doppler; Mixture thermal conductivity; Rod internal pressure; Dilute; Dense
topics (OpenAlex): Nuclear Materials and Properties; Nuclear reactor physics and engineering; Fusion materials and technologies
UN Sustainable Development Goals Color Wheel
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7. Affordable and Clean Energy (OpenAlex)
13. Climate Action (Web of Science)
Sources: Web Of Science, ORCID, NC State University Libraries, Crossref
Added: June 24, 2019

2018 journal article

Application of sub-channel modeling to BWR core analysis

ANNALS OF NUCLEAR ENERGY, 115, 294–302.

By: C. Gosdin* & M. Avramova n

author keywords: BWR; CTF; CASL; Sub-channel; Validation
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics; Nuclear and radioactivity studies
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Sources: Web Of Science, ORCID, NC State University Libraries
Added: August 6, 2018

2018 journal article

CFD prediction of critical heat flux in vertical heated tubes with uniform and non-uniform heat flux

NUCLEAR ENGINEERING AND DESIGN, 326, 403–412.

By: Q. Li, M. Avramova n, Y. Jiao, P. Chen, J. Yu*, Z. Pu, J. Chen

author keywords: Subcooled boiling; Critical heat flux; DNB; Non-uniform heat flux; Boiling curves
topics (OpenAlex): Heat Transfer and Boiling Studies; Fluid Dynamics and Mixing; Nuclear Engineering Thermal-Hydraulics
UN Sustainable Development Goals Color Wheel
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13. Climate Action (Web of Science)
Sources: Web Of Science, NC State University Libraries, Crossref
Added: August 6, 2018

2018 journal article

Implementation and assessment of wall friction models for LWR core analysis

ANNALS OF NUCLEAR ENERGY, 115, 565–572.

By: A. Toptan n, N. Porter n, R. Salko* & M. Avramova n

author keywords: Friction factor; CTF; Pressure drop; Subchannel analysis; Validation; Verification
topics (OpenAlex): Heat transfer and supercritical fluids; Nuclear Engineering Thermal-Hydraulics; Nuclear reactor physics and engineering
TL;DR: The modeling of frictional pressure drop in the nuclear thermal hydraulics subchannel code, CTF, is improved through the addition of three new modeling options which allow the code to account for the effects of surface roughness and the third enables a user-supplied option. (via Semantic Scholar)
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Sources: Web Of Science, NC State University Libraries
Added: August 6, 2018

2018 journal article

Quantified Validation with Uncertainty Analysis for Turbulent Single-Phase Friction Models

Porter, N. W., Mousseau, V. A., & Avramova, M. N. (2019, December 2). NUCLEAR TECHNOLOGY, Vol. 205, pp. 1607–1617.

By: N. Porter n, V. Mousseau* & M. Avramova n

author keywords: Model form error; uncertainty analysis; validation; friction factor
topics (OpenAlex): Probabilistic and Robust Engineering Design; Nuclear Engineering Thermal-Hydraulics; Nuclear reactor physics and engineering
Sources: Web Of Science, ORCID, NC State University Libraries, Crossref
Added: December 9, 2019

2018 journal article

Three-dimensional multi-physics modeling of hydrogen and hydride distribution in zirconium alloy cladding

PROGRESS IN NUCLEAR ENERGY, 105, 294–300.

By: M. Mankosa* & M. Avramova n

author keywords: Hydrogen; Hydride; Multi-physics; BISON; Tiamat
topics (OpenAlex): Nuclear Materials and Properties; Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics
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Sources: Web Of Science, ORCID, NC State University Libraries
Added: August 6, 2018

2018 journal article

Uncertainty Quantification Study of CTF for the OECD/NEA LWR Uncertainty Analysis in Modeling Benchmark

NUCLEAR SCIENCE AND ENGINEERING, 190(3), 271–286.

By: N. Porter n, M. Avramova n & V. Mousseau*

author keywords: Organisation for Economic Co-operation and Development/Nuclear Energy Agency Light Water Reactor Uncertainty Analysis in Modeling Benchmark; thermal hydraulics; CTF
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics; Probabilistic and Robust Engineering Design
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Sources: Web Of Science, ORCID, NC State University Libraries, Crossref
Added: August 6, 2018

2018 journal article

Validation of CTF pressure drop and void predictions for the NUPEC BWR database

NUCLEAR ENGINEERING AND DESIGN, 337, 291–299.

By: N. Porter n & M. Avramova n

topics (OpenAlex): Nuclear reactor physics and engineering; Heat transfer and supercritical fluids; Fluid Dynamics and Mixing
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Sources: Web Of Science, NC State University Libraries, Crossref
Added: October 16, 2018

2017 journal article

Comparative analysis of different fidelity fuel performance models for fuel temperature predictions

NUCLEAR ENGINEERING AND DESIGN, 322, 464–473.

By: F. Raja*, M. Mankosa* & M. Avramova n

author keywords: CTF; BISON; FRAPCON; Nuclear; Fuel performance
topics (OpenAlex): Heat transfer and supercritical fluids; Nuclear reactor physics and engineering; Nuclear Materials and Properties
UN Sustainable Development Goals Color Wheel
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7. Affordable and Clean Energy (OpenAlex)
Sources: Web Of Science, NC State University Libraries
Added: August 6, 2018

2017 journal article

Evaluation of modeling options for in-pellet power distribution and gap gas conductance for accurate fuel temperature predictions

PROGRESS IN NUCLEAR ENERGY, 100, 135–145.

By: F. Raja* & M. Avramova n

author keywords: CTF; FRAPCON; Nuclear; Fuel temperature; Gap gas conductance
topics (OpenAlex): Heat transfer and supercritical fluids; Thermal and Kinetic Analysis; Nuclear reactor physics and engineering
UN Sustainable Development Goals Color Wheel
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7. Affordable and Clean Energy (OpenAlex)
Sources: Web Of Science, ORCID, NC State University Libraries
Added: August 6, 2018

2017 journal article

High-fidelity multi-physics coupling for determination of hydride distribution in Zr-4 cladding

ANNALS OF NUCLEAR ENERGY, 110, 475–485.

By: I. Davis*, O. Courty*, M. Avramova n & A. Motta*

topics (OpenAlex): Nuclear Materials and Properties; Nuclear reactor physics and engineering; Fusion materials and technologies
UN Sustainable Development Goals Color Wheel
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Sources: Web Of Science, NC State University Libraries
Added: August 6, 2018

2017 journal article

Multi-physics code system with improved feedback modeling

PROGRESS IN NUCLEAR ENERGY, 98, 94–108.

By: M. Yilmaz*, M. Avramova n & J. Andersen*

author keywords: Doppler feedback; Fuel thermal conductivity degradation; Nudear reactor multi-physics; CTF/TORT-TD; CTF/TORT-TD/FRAPCON-FRAPTRAN
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Materials and Properties; Nuclear Engineering Thermal-Hydraulics
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Sources: Web Of Science, ORCID, NC State University Libraries
Added: August 6, 2018

2016 journal article

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

ANNALS OF NUCLEAR ENERGY, 96, 1–11.

By: A. Bennett n, M. Avramova n & K. Ivanov n

author keywords: MCNP6; CTF; Internal coupling; Relaxation acceleration
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Physics and Applications; Nuclear Materials and Properties
TL;DR: The relaxation acceleration technique was applied to the coupled code and was shown that it could satisfy much stricter convergence criterions and can also guarantee convergence and be used as a tool to decrease the computational time. (via Semantic Scholar)
UN Sustainable Development Goals Color Wheel
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Sources: Web Of Science, NC State University Libraries
Added: August 6, 2018

2016 journal article

Development, verification, and validation of a fuel thermal conductivity degradation model in CTF

ANNALS OF NUCLEAR ENERGY, 97, 246–261.

By: M. Yilmaz*, M. Avramova n & J. Andersen*

author keywords: Fuel thermal conductivity; Fuel centerline temperature; CTF; FRAPCON-3.4
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Materials and Properties; Nuclear Engineering Thermal-Hydraulics
UN Sustainable Development Goals Color Wheel
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Web Of Science, NC State University Libraries
Added: August 6, 2018

2016 journal article

Impact of fuel thermal conductivity degradation on Doppler feedback during rod ejection accident

NUCLEAR ENGINEERING AND DESIGN, 307, 339–353.

By: M. Yilmaz*, M. Avramova n & J. Andersen*

topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Materials and Properties; Nuclear Engineering Thermal-Hydraulics
UN Sustainable Development Goals Color Wheel
UN Sustainable Development Goal Categories
Sources: Web Of Science, NC State University Libraries
Added: August 6, 2018

2015 journal article

High-fidelity multi-physics system TORT-TD/CTF/FRAPTRAN for light water reactor analysis

Annals of Nuclear Energy, 84, 234–243.

By: J. Magedanz*, M. Avramova*, Y. Perin* & A. Velkov*

author keywords: Coupled codes; COBRA-TF; FRAPTRAN; High-fidelity; Fuel performance
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics; Nuclear Materials and Properties
Sources: Crossref, NC State University Libraries
Added: February 24, 2020

2015 journal article

Multi-physics and multi-scale benchmarking and uncertainty quantification within OECD/NEA framework

Annals of Nuclear Energy, 84, 178–196.

By: M. Avramova*, K. Ivanov*, T. Kozlowski*, I. Pasichnyk*, W. Zwermann*, K. Velkov*, E. Royer*, A. Yamaji*, J. Gulliford*

author keywords: Benchmark; Uncertainty; Multi-physics; Multi-scale
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics; Probabilistic and Robust Engineering Design
TL;DR: Second set of the NEA/OECD benchmarks have been initiated by the Expert Group on Uncertainty Analysis in Modelling (EGUAM) at the Nuclear Science Committee (NSC) to address the current trends in the development of LWR multi-physics and multi-scale modeling and simulation. (via Semantic Scholar)
Sources: Crossref, NC State University Libraries
Added: February 24, 2020

2015 journal article

Optimization and parallelization of the thermal–hydraulic subchannel code CTF for high-fidelity multi-physics applications

Annals of Nuclear Energy, 84, 122–130.

By: R. Salko*, R. Schmidt* & M. Avramova*

author keywords: Subchannel; COBRA-TF; Parallel; MPI; CTF
topics (OpenAlex): Nuclear reactor physics and engineering; Parallel Computing and Optimization Techniques; Superconducting Materials and Applications
TL;DR: Major improvements to the computational infrastructure of the CTF subchannel code are described so that full-core, pincell-resolved simulations can now be performed in much shorter run-times, either in stand-alone mode or as part of coupled-code multi-physics calculations. (via Semantic Scholar)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2014 journal article

Coupled 3D neutronics/thermal hydraulics modeling of the SAFARI-1 MTR

Annals of Nuclear Energy, 73, 122–130.

By: A. Rosenkrantz*, M. Avramova*, K. Ivanov*, R. Prinsloo*, D. Botes* & K. Elsakhawy*

topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Physics and Applications; Nuclear and radioactivity studies
TL;DR: A comparison allows for the first time to perform a quantification of steady-state errors for a low-powered MTR with an advanced thermal–hydraulic code such as CTF on a per-channel basis as compared to simpler and coarser-mesh RELAP5-3D modeling. (via Semantic Scholar)
UN Sustainable Development Goals Color Wheel
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2014 journal article

Investigations on coupled code PWR simulations using COBRA-TF with soluble boron tracking model

Progress in Nuclear Energy, 77, 72–83.

By: M. Biery* & M. Avramova*

author keywords: Boron dilution; Boron tracking model; Coupled code; Natural circulation
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics; Nuclear Materials and Properties
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2014 journal article

Multi-dimensional boron transport modeling in subchannel approach: Part I. Model selection, implementation and verification of COBRA-TF boron tracking model

Nuclear Engineering and Design, 278, 701–712.

By: O. Ozdemir*, M. Avramova* & K. Sato*

topics (OpenAlex): Nuclear Engineering Thermal-Hydraulics; Nuclear reactor physics and engineering; Nuclear Materials and Properties
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2014 journal article

Multi-dimensional boron transport modeling in subchannel approach: Part II. Validation of CTF boron tracking model and adding boron precipitation model

Nuclear Engineering and Design, 278, 713–722.

By: O. Ozdemir* & M. Avramova*

topics (OpenAlex): Nuclear Engineering Thermal-Hydraulics; Nuclear Materials and Properties; Nuclear reactor physics and engineering
UN Sustainable Development Goals Color Wheel
UN Sustainable Development Goal Categories
6. Clean Water and Sanitation (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2013 journal article

A multi-scale homogenization and reconstruction approach for solid material temperature calculations in prismatic high temperature reactor cores

Nuclear Engineering and Design, 256, 1–13.

By: I. Clifford*, K. Ivanov* & M. Avramova*

topics (OpenAlex): Advanced Mathematical Modeling in Engineering; Probabilistic and Robust Engineering Design; Advanced Numerical Methods in Computational Mathematics
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2013 journal article

New developments of the MCNP/CTF/NEM/NJOY code system – Monte Carlo based coupled code for high accuracy modeling

Annals of Nuclear Energy, 51, 18–26.

By: F. Espel*, M. Avramova*, K. Ivanov* & S. Misu*

author keywords: MCNP5; COBRA-TF; NEM; NJOY; Coupled calculations; BWR
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Materials and Properties; Nuclear Physics and Applications
TL;DR: This paper presents the latest studies and ameliorations developed to this coupled hybrid system, which includes a new methodology for generation and interpolation of Temperature-Dependent Thermal Scattering Cross Section Libraries for MCNP5, a comparison between sub-channel approaches, and acceleration schemes. (via Semantic Scholar)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2013 journal article

Uncertainty analysis of sub-channel code calculated ONB wall superheat in rod bundle experiments using the GRS methodology

Progress in Nuclear Energy, 65, 42–49.

By: R. Salko* & M. Avramova*

author keywords: VIPRE-I; SUSA; NESTOR; ONB
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics; Nuclear Materials and Properties
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2010 journal article

Verification, validation and uncertainty quantification in multi-physics modeling for nuclear reactor design and safety analysis

Progress in Nuclear Energy, 52(7), 601–614.

By: M. Avramova* & K. Ivanov*

author keywords: Verification; Validation; Uncertainty; Design; Analysis
topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics; Probabilistic and Robust Engineering Design
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2007 journal article

Challenges in coupled thermal–hydraulics and neutronics simulations for LWR safety analysis

Annals of Nuclear Energy, 34(6), 501–513.

By: K. Ivanov* & M. Avramova*

topics (OpenAlex): Nuclear reactor physics and engineering; Nuclear Engineering Thermal-Hydraulics; Nuclear Materials and Properties
TL;DR: The issues related to the consistent qualification of coupled code systems as well as their application to different types of LWR transients are presented and the advances in numerical and computation techniques for coupled code simulations are summarized with outlining remaining challenges. (via Semantic Scholar)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2006 journal article

Evaluation and enhancement of COBRA-TF efficiency for LWR calculations

Annals of Nuclear Energy, 33(9), 837–847.

By: D. Cuervo*, M. Avramova*, K. Ivanov* & R. Miró*

topics (OpenAlex): Nuclear reactor physics and engineering; Computational Fluid Dynamics and Aerodynamics; Advanced Numerical Methods in Computational Mathematics
TL;DR: Results indicate that the direct inversion method is the best option for small cases, while both new solvers converge smoothly regardless of the nature of simulated cases and the mesh structures and improve the stability and accuracy of results compared to the classic Gauss–Seidel iterative method. (via Semantic Scholar)
UN Sustainable Development Goals Color Wheel
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

Employment

Updated: March 27th, 2025 10:29

2021 - present

North Carolina State University Raleigh, North Carolina, US
Professor and University Faculty Scholar Nuclear Engineering

2015 - 2021

North Carolina State University Raleigh, North Carolina, US
Associate Professor Nuclear Engineering

2015 - 2018

Pennsylvania State University State College, Pennsylvania, US
Adjunct Professor and Member of Graduate School Mechanical and Nuclear Engineering Department

2015 - 2015

Pennsylvania State University State College, Pennsylvania, US
Associate Professor Mechanical and Nuclear Engineering Department

2009 - 2015

Pennsylvania State University State College, Pennsylvania, US
Assistant Professor Mechanical and Nuclear Engineering Department

2008 - 2008

Pennsylvania State University State College, Pennsylvania, US
Post-Doctoral Scholar Mechanical and Nuclear Engineering Department

2001 - 2007

Pennsylvania State University State College, Pennsylvania, US
Graduate Research Assistant Mechanical and Nuclear Engineering Department

1994 - 2000

Bulgarian Academy of Sciences Sofia, Sofia-Capital, BG
Research Scientist Institute for Nuclear Research and Nuclear Energy

Education

Updated: March 27th, 2025 10:36

2003 - 2007

Pennsylvania State University State College, Pennsylvania, US
Ph.D., Nuclear Engineering Mechanical and Nuclear Engineering Department

2001 - 2003

Pennsylvania State University State College, Pennsylvania, US
M.S., Nuclear Engineering Mechanical and Nuclear Engineering Department

1986 - 1993

Sofia University "St. Kliment Ohridski" Sofia, Sofia-Capital, BG
B.S./M.S., Engineering Physics Physics

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