Maria Nikolova Avramova

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

NUCLEAR ENGINEERING AND DESIGN, 435.

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

APPLIED SCIENCES-BASEL, 14(17).

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

NUCLEAR ENGINEERING AND DESIGN, 430.

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.

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.

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.

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

Frontiers in Energy Research, 11.

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

EPJ Nuclear Sciences & Technologies, 9, 15.

A Three-Dimensional Cartesian Thermal-Hydraulic Solver in the Residual Formulation of CTF

Proceedings: 2022 ANS Winter Meeting. Presented at the 2022 ANS Winter Meeting, Phoenix, AZ, USA.

Ab initio molecular dynamics investigation of <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" altimg="si2.svg"><mml:mi>γ</mml:mi></mml:math>-(U,Zr) structural and thermal properties as a function of temperature and composition

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.

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

Energies, 15(14), 5226.

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.

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

Development of a Steady-State Solver and Non-Linear Iteration Structure in the Residual Formulation of CTF

Proceedings: The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19). Presented at the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), Brussels, Belgium.

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, 108715.

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

Annals of Nuclear Energy, 177, 109277.

Fuel Performance Uncertainty Quantification and Sensitivity Analysis Methodology for Aleatoric and Epistemic Sources of Uncertainties

Proceedings: 2022 ANS Winter Meeting. Presented at the 2022 ANS Winter Meeting, Phoenix, AZ, USA.

High-to-Low Multi-Physics Modeling and Uncertainty Propagation Using NEAMS Tools”

High-to-Low Multi-Physics Modeling and Uncertainty Propagation Using NEAMS Tools.” Proceedings: 2022 ANS Winter Meeting. Presented at the 2022 ANS Winter Meeting, Phoenix, AZ, USA.

Integral Benchmark Evaluation Of Zero-Power Tests And Multi-Cycle Depletion Experimental Data Of TVA Wb1 Cycles 1-3

Proceedings: 2022 ANS Winter Meeting. Presented at the 2022 ANS Winter Meeting, Phoenix, AZ, USA.

Introducing the OECD/NEA WPRS Task Force on Artificial Intelligence and Machine Learning

Proceedings: 2022 ANS Winter Meeting. Presented at the 2022 ANS Winter Meeting, Phoenix, AZ, USA.

Investigation of <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" altimg="si2.svg"><mml:mi>γ</mml:mi></mml:math>-<mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" altimg="si12.svg"><mml:mrow><mml:mo>(</mml:mo><mml:mi>U</mml:mi><mml:mo>,</mml:mo><mml:mi>Z</mml:mi><mml:mi>r</mml:mi><mml:mo>)</mml:mo></mml:mrow></mml:math> structural properties and its interfacial properties with liquid sodium using ab initio molecular dynamics

Investigation of ?-(U, Zr) structural properties and its interfacial properties with liquid sodium using ab initio molecular dynamics. JOURNAL OF NUCLEAR MATERIALS, 567.

Investigation of Different Planar Averaging Techniques in NEK5000 for High-to-Low Information of CTF

Proceedings: The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19). Presented at the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), Brussels, Belgium.

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

OECD/NEA MPCMIV Benchmark -- Preliminary Fuel Performance Results

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

Annals of Nuclear Energy, 178, 109344.

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

Propagation of VHTRC manufacturing uncertainties with RAVEN/PHISICS

Annals of Nuclear Energy, 165, 108667.

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

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

Why is Uncertainty Quantification Important for Machine Learning Models?

Proceedings: 2022 ANS Winter Meeting. Presented at the 2022 ANS Winter Meeting, Phoenix, AZ, USA.

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

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

Annals of Nuclear Energy, 150, 107861.

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

Annals of Nuclear Energy, 163, 108548.

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

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

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

Nuclear Engineering and Design, 384, 111474.

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

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

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

Nuclear Engineering and Design, 358, 110387.

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

Nuclear Engineering and Design, 362, 110526.

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

Nuclear Engineering and Design, 369, 110826.

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

Nuclear Engineering and Design, 341, 248–258.

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

Annals of Nuclear Energy, 131, 51–62.

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

Nuclear Engineering and Design, 348, 37–45.

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

Nuclear Engineering and Design, 353, 110283.

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

Nuclear Engineering and Design, 355, 110289.

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

Nuclear Engineering and Design, 350, 1–8.

Application of sub-channel modeling to BWR core analysis

ANNALS OF NUCLEAR ENERGY, 115, 294–302.

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

Nuclear Engineering and Design, 326, 403–412.

Development, verification and application of a new model for active nucleation site density in boiling systems

Nuclear Engineering and Design, 328, 1–9.

Implementation and assessment of wall friction models for LWR core analysis

ANNALS OF NUCLEAR ENERGY, 115, 565–572.

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

Nuclear Technology, 205(12), 1607–1617.

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

PROGRESS IN NUCLEAR ENERGY, 105, 294–300.

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

Nuclear Science and Engineering, 190(3), 271–286.

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

Nuclear Engineering and Design, 337, 291–299.

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

NUCLEAR ENGINEERING AND DESIGN, 322, 464–473.

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.

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

ANNALS OF NUCLEAR ENERGY, 110, 475–485.

Multi-physics code system with improved feedback modeling

PROGRESS IN NUCLEAR ENERGY, 98, 94–108.

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

ANNALS OF NUCLEAR ENERGY, 96, 1–11.

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

ANNALS OF NUCLEAR ENERGY, 97, 246–261.

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

NUCLEAR ENGINEERING AND DESIGN, 307, 339–353.

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

Annals of Nuclear Energy, 84, 234–243.

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

Annals of Nuclear Energy, 84, 178–196.

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

Annals of Nuclear Energy, 84, 122–130.

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

Annals of Nuclear Energy, 73, 122–130.

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

Progress in Nuclear Energy, 77, 72–83.

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.

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.

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.

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.

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.

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

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

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

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

Evaluation and enhancement of COBRA-TF efficiency for LWR calculations

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