Works (64)
2025 journal article
BWR core thermal-hydraulic uncertainty and sensitivity analysis with improved bypass modeling features
NUCLEAR ENGINEERING AND DESIGN, 435.

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).
2024 journal article
Fuel performance code to code comparative analysis for the OECD/NEA MPCMIV benchmark
NUCLEAR ENGINEERING AND DESIGN, 430.
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.
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.

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.

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.

2023 journal article
Preservation of kinetics parameters generated by Monte Carlo calculations in two-step deterministic calculations
EPJ Nuclear Sciences & Technologies, 9, 15.

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.

2022 journal article
CTF-PARCS Core Multi-Physics Computational Framework for Efficient LWR Steady-State, Depletion and Transient Uncertainty Quantification
Energies, 15(14), 5226.

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.

2022 article proceedings
Development of a High-Fidelity Multi-Physics Coupling Between MCNP6.2 and CTF4.0 for VVER Applications

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

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.

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.

2022 article proceedings
Machine Learning-Based Prediction of Departure from Nucleate Boiling Power for the PSBT Benchmark
2022 article proceedings
OECD/NEA MPCMIV Benchmark -- Preliminary Fuel Performance Results
2022 journal article
Off-line vs. semi-implicit TH-TH coupling schemes: A BEPU comparison
ANNALS OF NUCLEAR ENERGY, 178.

2022 article proceedings
Phase I Specifications and Preliminary Sensitivity Analyses of the OECD-NRC Liquid Metal Fast Reactor Core Thermal-Hydraulics Benchmark
2022 journal article
Propagation of VHTRC manufacturing uncertainties with RAVEN/PHISICS
Annals of Nuclear Energy, 165, 108667.

2022 article proceedings
Quantification of the Importance of the Modeling Fidelity in the Best Estimate Plus Uncertainty Analysis
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

2022 article proceedings
julia for Enhancing Nuclear Engineering Simulations (JENES): Introduction to the JENES Project and Platform
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, n , A. Gupta n, R. Youngblood *, J. Lane *, N. Dinh n

2021 journal article
Development and verification of a higher-order mathematical adjoint nodal diffusion solver
Annals of Nuclear Energy, 163, 108548.

2021 journal article
Innovations in Multi-Physics Methods Development, Validation, and Uncertainty Quantification
Journal of Nuclear Engineering, 2(1), 44–56.
2021 journal article
Summary of comparative analysis and conclusions from OECD/NEA LWR-UAM benchmark Phase I
Nuclear Engineering and Design, 384, 111474.

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.

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.

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.

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.
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.

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.

2019 journal article
CTF-R: A novel residual-based thermal hydraulic solver
NUCLEAR ENGINEERING AND DESIGN, 348, 37–45.
2019 journal article
Gap conductance modeling I: Theoretical considerations for single- and multi-component gases in curvilinear coordinates
NUCLEAR ENGINEERING AND DESIGN, 353.

2019 journal article
Gap conductance modeling II: Optimized model for UO2-Zircaloy interfaces
NUCLEAR ENGINEERING AND DESIGN, 355.

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.

2018 journal article
Application of sub-channel modeling to BWR core analysis
ANNALS OF NUCLEAR ENERGY, 115, 294–302.

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.

2018 journal article
Implementation and assessment of wall friction models for LWR core analysis
ANNALS OF NUCLEAR ENERGY, 115, 565–572.

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.
2018 journal article
Three-dimensional multi-physics modeling of hydrogen and hydride distribution in zirconium alloy cladding
PROGRESS IN NUCLEAR ENERGY, 105, 294–300.

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.

2018 journal article
Validation of CTF pressure drop and void predictions for the NUPEC BWR database
NUCLEAR ENGINEERING AND DESIGN, 337, 291–299.

2017 journal article
Comparative analysis of different fidelity fuel performance models for fuel temperature predictions
NUCLEAR ENGINEERING AND DESIGN, 322, 464–473.

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.

2017 journal article
High-fidelity multi-physics coupling for determination of hydride distribution in Zr-4 cladding
ANNALS OF NUCLEAR ENERGY, 110, 475–485.

2017 journal article
Multi-physics code system with improved feedback modeling
PROGRESS IN NUCLEAR ENERGY, 98, 94–108.

2016 journal article
Coupled MCNP6/CTF code: Development, testing, and application
ANNALS OF NUCLEAR ENERGY, 96, 1–11.

2016 journal article
Development, verification, and validation of a fuel thermal conductivity degradation model in CTF
ANNALS OF NUCLEAR ENERGY, 97, 246–261.

2016 journal article
Impact of fuel thermal conductivity degradation on Doppler feedback during rod ejection accident
NUCLEAR ENGINEERING AND DESIGN, 307, 339–353.

2015 journal article
High-fidelity multi-physics system TORT-TD/CTF/FRAPTRAN for light water reactor analysis
Annals of Nuclear Energy, 84, 234–243.
2015 journal article
Multi-physics and multi-scale benchmarking and uncertainty quantification within OECD/NEA framework
Annals of Nuclear Energy, 84, 178–196.
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.
2014 journal article
Coupled 3D neutronics/thermal hydraulics modeling of the SAFARI-1 MTR
Annals of Nuclear Energy, 73, 122–130.

2014 journal article
Investigations on coupled code PWR simulations using COBRA-TF with soluble boron tracking model
Progress in Nuclear Energy, 77, 72–83.
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.
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.

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.
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.
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.
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.
2007 journal article
Challenges in coupled thermal–hydraulics and neutronics simulations for LWR safety analysis
Annals of Nuclear Energy, 34(6), 501–513.
2006 journal article
Evaluation and enhancement of COBRA-TF efficiency for LWR calculations
Annals of Nuclear Energy, 33(9), 837–847.

Employment
Updated: March 27th, 2025 10:29
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Education
Updated: March 27th, 2025 10:36
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