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
Clustering and uncertainty analysis to improve the machine learning-based predictions of SAFARI-1 control follower assembly axial neutron flux profiles
ANNALS OF NUCLEAR ENERGY, 206.
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.
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
Prediction and uncertainty quantification of SAFARI-1 axial neutron flux profiles with neural networks
ANNALS OF NUCLEAR ENERGY, 188.
2023 journal article
Preservation of kinetics parameters generated by Monte Carlo calculations in two-step deterministic calculations
EPJ NUCLEAR SCIENCES & TECHNOLOGIES, 9.
2022 journal article
A hybrid neutronics method with novel fission diffusion synthetic acceleration for criticality calculations
NUCLEAR ENGINEERING AND TECHNOLOGY, 55(4), 1428–1438.
2022 journal article
CTF-PARCS Core Multi-Physics Computational Framework for Efficient LWR Steady-State, Depletion and Transient Uncertainty Quantification
ENERGIES, 15(14).
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.
2021 journal article
Development and verification of a higher-order mathematical adjoint nodal diffusion solver
ANNALS OF NUCLEAR ENERGY, 163.
2021 journal article
Evidence-based background for constrained uncertainty quantification in a core transient analysis
ANNALS OF NUCLEAR ENERGY, 164.
2021 journal article
Methodology for Discontinuity Factors Generation for Simplified P-3 Solver Based on Nodal Expansion Formulation
ENERGIES, 14(20).
2021 journal article
Propagation of VHTRC manufacturing uncertainties with RAVEN/PHISICS
ANNALS OF NUCLEAR ENERGY, 165.
2021 journal article
Summary of comparative analysis and conclusions from OECD/NEA LWR-UAM benchmark Phase I
NUCLEAR ENGINEERING AND DESIGN, 384.
2019 journal article
Energy group search engine based on surrogate models constructed with the RAVEN/NEWT/PHISICS sequence
NUCLEAR ENGINEERING AND DESIGN, 356.
2019 journal article
Quantification and propagation of neutronics uncertainties of the Kozloduy-6 VVER-1000 fuel assembly using SCALE 6.2.1 within the NEA/OECD benchmark for uncertainty analysis in modelling of LWRs
ANNALS OF NUCLEAR ENERGY, 133, 732–749.
2019 article
Selected papers from the 2018 Best Estimate Plus Uncertainty International Conference (BEPU 2018) Foreword
Petruzzi, A., Ivanov, K., & Ivanov, E. (2019, December 2). NUCLEAR TECHNOLOGY, Vol. 205, pp. III-IV.
2019 journal article
Uncertainty Quantification and Propagation of Multiphysics Simulation of the Pressurized Water Reactor Core
Nuclear Technology, 205(12), 1618–1637.
2018 journal article
The IAEA CRP on HTGR uncertainties: Sensitivity study of PHISICS/RELAP5-3D MHTGR-350 core calculations using various SCALE/NEWT cross-section sets for Ex. II-1a
Nuclear Engineering and Design, 329, 156–166.
2017 journal article
Comparison of Best-Estimate Plus Uncertainty and Conservative Methodologies for a PWR MSLB Analysis Using a Coupled 3-D Neutron-Kinetics/Thermal-Hydraulic Code
Nuclear Technology, 198(2), 193–201.
2017 journal article
New techniques for designing the initial and reload cores with constant long cycle lengths
Annals of Nuclear Energy, 99, 165–173.
2017 journal article
OECD/NEA benchmark for time-dependent neutron transport calculations without spatial homogenization
NUCLEAR ENGINEERING AND DESIGN, 317, 177–189.
2016 journal article
Advances in the Pennsylvania State University NEM code
ANNALS OF NUCLEAR ENERGY, 94, 251–262.
2016 conference paper
Benchmarking the NEM real-time core model for VVER-1000 simulator application - asymmetric core
Proceedings of the 24th International Conference on Nuclear Engineering, 2016, vol 5.
2016 journal article
Benchmarking the Real-Time Core Model for VVER-1000 Simulator Application on Asymmetric Core Load
JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 3(3).
2016 journal article
Coupled MCNP6/CTF code: Development, testing, and application
ANNALS OF NUCLEAR ENERGY, 96, 1–11.
2016 journal article
Rod Internal Pressure Distribution and Uncertainty Analysis Using FRAPCON
NUCLEAR TECHNOLOGY, 197(1), 47–63.
2016 article
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, September). NUCLEAR ENGINEERING AND DESIGN, Vol. 306, pp. 77–88.
2015 journal article
Code improvement and model validation for Ascó-II Nuclear Power Plant model using a coupled 3D neutron kinetics/thermal–hydraulic code
Annals of Nuclear Energy, 87, 366–374.
2015 journal article
Examination and refinement of fine energy group structure for high temperature reactor analysis
Annals of Nuclear Energy, 80, 279–292.
2015 journal article
Large-scale Monte Carlo neutron transport calculations with thermal hydraulic feedback
Annals of Nuclear Energy, 84, 204–219.
2015 journal article
Multi-physics and multi-scale benchmarking and uncertainty quantification within OECD/NEA framework
Annals of Nuclear Energy, 84, 178–196.
2014 journal article
A cycle-specific cross-section update for real-time simulation of VVER-1000 core
Progress in Nuclear Energy, 74, 222–231.
2014 journal article
ASSESSMENT OF MICROX-2 CODE WITH NEW ENDF/B-VII RELEASE 0 MASTER LIBRARIES
NUCLEAR TECHNOLOGY, 186(3), 305–316.
2014 journal article
Coupled 3D neutronics/thermal hydraulics modeling of the SAFARI-1 MTR
Annals of Nuclear Energy, 73, 122–130.
2014 journal article
Development of an iterative diffusion-transport method based on MICROX-2 cross section libraries
ANNALS OF NUCLEAR ENERGY, 77, 335–342.
2014 conference paper
High-Fidelity Coupled Monte-Carlo/Thermal-Hydraulics Calculations
In D. Caruge, C. Calvin, C. M. Diop, F. Malvagi, & J.-C. Trama (Eds.), SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo.
Ed(s): D. Caruge, C. Calvin, C. Diop, F. Malvagi & J. Trama
Event: SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo
2014 journal article
Internal multi-scale multi-physics coupled system for high fidelity simulation of light water reactors
Annals of Nuclear Energy, 66, 104–112.
2014 conference paper
Iterative Transport-Diffusion Methodology For LWR Core Analysis
In D. Caruge, C. Calvin, C. M. Diop, F. Malvagi, & J.-C. Trama (Eds.), SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo.
Ed(s): D. Caruge, C. Calvin, C. Diop, F. Malvagi & J. Trama
Event: SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo
2014 journal article
Multi-group formulation of the temperature-dependent resonance scattering model and its impact on reactor core parameters
Annals of Nuclear Energy, 63, 751–762.
2014 journal article
Self-shielding models of MICROX-2 code: Review and updates
ANNALS OF NUCLEAR ENERGY, 64, 256–263.
2014 journal article
The effect of changing enrichments on core performance
Annals of Nuclear Energy, 75, 139–145.
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
Analysis of the OECD/NRC Oskarshamn-2 BWR stability benchmark
Annals of Nuclear Energy, 67, 4–12.
2013 journal article
High fidelity simulation of conventional and innovative LWR with the coupled Monte-Carlo thermal-hydraulic system MCNP-SUBCHANFLOW
Nuclear Engineering and Design, 262, 264–275.
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
Progress in the development of an implicit steady state solution in the coupled code TRACE/PARCS
Progress in Nuclear Energy, 66, 1–12.
2013 journal article
Understanding using the Haling Power Depletion (HPD) as a guide for designing PWR cores
Annals of Nuclear Energy, 53, 120–128.
2012 journal article
DYNSUB: A high fidelity coupled code system for the evaluation of local safety parameters – Part I: Development, implementation and verification
Annals of Nuclear Energy, 48, 108–122.
2012 journal article
DYNSUB: A high fidelity coupled code system for the evaluation of local safety parameters – Part II: Comparison of different temporal schemes
Annals of Nuclear Energy, 48, 123–129.
2011 journal article
Deterministic modeling of higher angular moments of resonant neutron scattering
Annals of Nuclear Energy, 38(10), 2291–2297.
2011 journal article
MCOR – Monte Carlo depletion code for reference LWR calculations
Annals of Nuclear Energy, 38(4), 731–741.
2010 journal article
Application of Global Sensitivity Analysis to Nuclear Reactor Calculations
Procedia - Social and Behavioral Sciences, 2(6), 7726–7727.
2010 journal article
Spectral zone selection methodology for pebble bed reactors
Annals of Nuclear Energy, 38(1), 80–87.
2010 journal article
Transport model based on three-dimensional cross-section generation for TRIGA core analysis
Annals of Nuclear Energy, 37(9), 1254–1260.
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.
2009 journal article
Application of TRACE/PARCS to BWR stability analysis
Annals of Nuclear Energy, 36(3), 317–323.
2008 journal article
Development of a practical Monte Carlo based fuel management system for the Penn State University Breazeale Research Reactor (PSBR)
Annals of Nuclear Energy, 35(3), 539–551.
2008 journal article
Evaluation of PBMR control rod worth using full three-dimensional deterministic transport methods
Annals of Nuclear Energy, 35(6), 1050–1055.
2008 journal article
New genetic algorithms (GA) to optimize PWR reactors
Annals of Nuclear Energy, 35(1), 113–120.
2007 journal article
Accuracy evaluation of pin exposure calculations in current LWR core design codes
Annals of Nuclear Energy, 35(3), 414–424.
2007 journal article
Challenges in coupled thermal–hydraulics and neutronics simulations for LWR safety analysis
Annals of Nuclear Energy, 34(6), 501–513.
2007 journal article
New genetic algorithms (GA) to optimize PWR reactors
Annals of Nuclear Energy, 35(1), 93–112.
2007 journal article
New genetic algorithms (GA) to optimize PWR reactors
Annals of Nuclear Energy, 35(1), 121–131.
2007 journal article
The three-dimensional neutron kinetics coupled with thermal-hydraulics in RBMK accident analysis
Nuclear Engineering and Design, 238(4), 1002–1025.
2007 journal article
Utilization of two-dimensional deterministic transport methods for analysis of pebble-bed reactors
Annals of Nuclear Energy, 34(5), 396–405.
2006 journal article
Analysis of the VVER1000 coolant trip benchmark using the coupled RELAP5/PARCS code
Progress in Nuclear Energy, 48(8), 806–819.
2006 journal article
Application of genetic algorithms to optimize burnable poison placement in pressurized water reactors
Annals of Nuclear Energy, 33(5), 446–456.
2006 journal article
Comparative RELAP5-3D analysis in support of the NPP DBA analysis in Ukraine
Progress in Nuclear Energy, 48(8), 891–911.
2006 journal article
Development of enriched Gd-155 and Gd-157 burnable poison designs for a PWR core
Annals of Nuclear Energy, 33(5), 439–445.
2006 journal article
Evaluation and enhancement of COBRA-TF efficiency for LWR calculations
Annals of Nuclear Energy, 33(9), 837–847.
2006 journal article
Impact of cross-section generation procedures on the simulation of the VVER-1000 pump startup experiment in the OECD/DOE/CEA V1000CT benchmark by coupled 3D thermal-hydraulics/neutron kinetics models
Progress in Nuclear Energy, 48(8), 746–763.
2006 journal article
Introduction to the special issue on the OECD/DOE/CEA V1000CT-1 benchmark
Progress in Nuclear Energy, 48(8), 727.
2006 journal article
Modeling and optimization of existing beam port facility of PSBR
Annals of Nuclear Energy, 33(17-18), 1391–1395.
2006 journal article
OECD/DOE/CEA VVER-1000 coolant transient (V1000CT) benchmark – A consistent approach for assessing coupled codes for RIA analysis
Progress in Nuclear Energy, 48(8), 728–745.
2006 journal article
Sensitivity study on determining an efficient set of fuel assembly parameters in training data for designing of neural networks in hybrid genetic algorithms
Annals of Nuclear Energy, 33(5), 457–465.
2006 journal article
Simulation of the VVER-1000 pump start-up experiment of the OECD V1000CT benchmark with CATHARE and TRAC-PF1
Progress in Nuclear Energy, 48(8), 922–936.
2006 journal article
The PBMR steady-state and coupled kinetics core thermal-hydraulics benchmark test problems
Nuclear Engineering and Design, 236(5-6), 657–668.
2004 journal article
Helios, current coupling collision probability method, applied for solving the NEA C5G7 MOX benchmark
Progress in Nuclear Energy, 45(2-4), 119–124.
2003 journal article
Development of the VVER core loading optimization system
Annals of Nuclear Energy, 31(7), 747–772.
2003 journal article
Minimizing the gamma radiation effects to spent fuel pool walls
Annals of Nuclear Energy, 31(5), 459–480.
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