Works (82)

Updated: October 8th, 2024 07:06

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
Sources: ORCID, Web Of Science, NC State University Libraries
Added: September 1, 2024

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.

By: L. Moloko n, P. Bokov n, X. Wu n & K. Ivanov n

author keywords: Deep Neural Networks; Uncertainty Quantification; Monte Carlo Dropout; Clustering analysis; Gaussian Process
Sources: Web Of Science, NC State University Libraries, ORCID
Added: June 1, 2024

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
Sources: Web Of Science, NC State University Libraries
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.

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
UN Sustainable Development Goal Categories
Sources: Web Of Science, NC State University Libraries
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)
Sources: Web Of Science, NC State University Libraries
Added: April 17, 2023

2023 journal article

Prediction and uncertainty quantification of SAFARI-1 axial neutron flux profiles with neural networks

ANNALS OF NUCLEAR ENERGY, 188.

By: L. Moloko n, P. Bokov n, X. Wu n & K. Ivanov n

author keywords: Uncertainty quantification; Deep neural networks; Bayesian Neural Networks; Monte Carlo dropout
TL;DR: Deep Neural Networks are used to predict the assembly axial neutron flux profiles in the SAFARI-1 research reactor with quantified uncertainties in the ANN predictions and extrapolation to cycles not used in the training process, indicating good prediction and generalization capability. (via Semantic Scholar)
Sources: ORCID, Web Of Science, NC State University Libraries
Added: March 23, 2023

2023 journal article

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

EPJ NUCLEAR SCIENCES & TECHNOLOGIES, 9.

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)
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Web Of Science, NC State University Libraries
Added: March 27, 2023

2022 journal article

A hybrid neutronics method with novel fission diffusion synthetic acceleration for criticality calculations

NUCLEAR ENGINEERING AND TECHNOLOGY, 55(4), 1428–1438.

By: J. Chen n, J. Hou n & K. Ivanov n

author keywords: Monte Carlo; Hybrid neutronics method; Diffusion synthetic acceleration
Sources: ORCID, Web Of Science, NC State University Libraries
Added: December 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).

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
UN Sustainable Development Goal Categories
6. Clean Water and Sanitation (OpenAlex)
Sources: Web Of Science, NC State University Libraries, ORCID
Added: July 20, 2022

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.

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

author keywords: Nodal Expansion Method (NEM); Adjoint Lagrange Multiplier; Axial Offset (AO); Perturbation analysis; Sensitivity analysis; IAEA
UN Sustainable Development Goal Categories
Sources: Web Of Science, NC State University Libraries
Added: May 30, 2023

2021 journal article

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

ANNALS OF NUCLEAR ENERGY, 163.

By: M. Altahhan n, R. 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
UN Sustainable Development Goal Categories
Sources: Web Of Science, NC State University Libraries
Added: September 7, 2021

2021 journal article

Evidence-based background for constrained uncertainty quantification in a core transient analysis

ANNALS OF NUCLEAR ENERGY, 164.

By: E. Ivanov*, A. Sargeni*, K. Ivanov n & G. Bruna

author keywords: Multi-physics modeling; Validation and uncertainty quantification; UAM-LWR; Data assimilation
TL;DR: Combining experiments-grounded and calibrated uncertainties, the last phase – constrained uncertainty propagation – was illustrated with an example of one international standard problem on transient initiated in LWR core by inadvertent Control Rod ejection. (via Semantic Scholar)
UN Sustainable Development Goal Categories
16. Peace, Justice and Strong Institutions (OpenAlex)
Sources: Web Of Science, NC State University Libraries
Added: October 26, 2021

2021 journal article

Methodology for Discontinuity Factors Generation for Simplified P-3 Solver Based on Nodal Expansion Formulation

ENERGIES, 14(20).

By: Y. Xu n, J. Hou n & K. Ivanov n

author keywords: transport-corrected SP3; nodal expansion method; generalized equivalence theory; discontinuity factors
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Web Of Science, ORCID, NC State University Libraries
Added: October 11, 2021

2021 journal article

Propagation of VHTRC manufacturing uncertainties with RAVEN/PHISICS

ANNALS OF NUCLEAR ENERGY, 165.

author keywords: PHISICS; RAVEN; VHTRC; Manufacturing Uncertainties; Monte Carlo Sampling
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Web Of Science, NC State University Libraries
Added: November 8, 2021

2021 journal article

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

NUCLEAR ENGINEERING AND DESIGN, 384.

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

author keywords: LWR; Uncertainty analysis; Benchmark; Neutronics; Summary
UN Sustainable Development Goal Categories
6. Clean Water and Sanitation (OpenAlex)
Sources: Web Of Science, NC State University Libraries, ORCID
Added: October 1, 2021

2019 journal article

Energy group search engine based on surrogate models constructed with the RAVEN/NEWT/PHISICS sequence

NUCLEAR ENGINEERING AND DESIGN, 356.

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

author keywords: PHISICS; NEWT; High Temperature Gas-cooled Reactors; Group structure; Adaptive sampling; RAVEN
TL;DR: An automated sequence that searches for suitable coarse-group configurations and derives a few six-group structures fitting the HTTR model, tested on a simplified two-dimensional HTTR core model. (via Semantic Scholar)
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Web Of Science, NC State University Libraries
Added: January 13, 2020

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.

By: G. Nyalunga*, V. Naicker* & K. Ivanov n

Sources: Web Of Science, NC State University Libraries
Added: September 30, 2019

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.

By: A. Petruzzi*, K. Ivanov n & E. Ivanov*

Sources: Web Of Science, NC State University Libraries
Added: December 9, 2019

2019 journal article

Uncertainty Quantification and Propagation of Multiphysics Simulation of the Pressurized Water Reactor Core

Nuclear Technology, 205(12), 1618–1637.

By: K. Zeng n, J. Hou n, K. Ivanov n & M. Jessee*

author keywords: Uncertainty quantification; stochastic sampling; PWR; rod ejection accident; multiphysics simulation
UN Sustainable Development Goal Categories
Sources: Crossref, NC State University Libraries, ORCID
Added: May 24, 2019

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.

author keywords: PHISICS/RELAP5-3D; TRITON/NEWT; High Temperature Gas-cooled Reactors; Neutron flux spectrum; Super cells; Cross section libraries; Power density
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: February 24, 2020

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.

By: R. Pericas*, K. Ivanov*, F. Reventós* & L. Batet*

author keywords: Safety analysis; coupled NK-TH; best-estimate plus uncertainty
UN Sustainable Development Goal Categories
6. Clean Water and Sanitation (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: February 24, 2020

2017 journal article

New techniques for designing the initial and reload cores with constant long cycle lengths

Annals of Nuclear Energy, 99, 165–173.

By: J. Shi*, S. Levine* & K. Ivanov n

author keywords: Low leakage core; Haling power depletion; Burnable poisons; Peak pin power; Fuel cost
UN Sustainable Development Goal Categories
Sources: Crossref, NC State University Libraries
Added: February 24, 2020

2017 journal article

OECD/NEA benchmark for time-dependent neutron transport calculations without spatial homogenization

NUCLEAR ENGINEERING AND DESIGN, 317, 177–189.

By: J. Hou n, K. Ivanov n, V. Boyarinov* & P. Fomichenko*

author keywords: Neutron transients; Space-time benchmark C5G7-TD; Kinetics parameters
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Web Of Science, NC State University Libraries, ORCID
Added: August 6, 2018

2016 journal article

Advances in the Pennsylvania State University NEM code

ANNALS OF NUCLEAR ENERGY, 94, 251–262.

By: S. Thompson* & K. Ivanov n

author keywords: SP3; MOX; Nodal expansion method; Neutron diffusion; Transverse leakage
TL;DR: The Pennsylvania State University NEM code has been updated in an attempt to enable the code to model more neutronically complex reactor cores, such as those containing mixed-oxide fuel, low leakage cores, and cores that contain multiple burnable poison types. (via Semantic Scholar)
UN Sustainable Development Goal Categories
Sources: Web Of Science, NC State University Libraries
Added: August 6, 2018

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.

By: E. Georgieva*, Y. Dinkov*, K. Ivanov n & R. Stieglitz*

UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: NC State University Libraries, NC State University Libraries
Added: August 6, 2018

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).

By: E. Georgieva*, Y. Dinkov* & K. Ivanov n

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

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
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 Goal Categories
Sources: Web Of Science, NC State University Libraries
Added: August 6, 2018

2016 journal article

Rod Internal Pressure Distribution and Uncertainty Analysis Using FRAPCON

NUCLEAR TECHNOLOGY, 197(1), 47–63.

By: R. Bratton*, M. Jessee*, W. Wieselquist* & K. Ivanov n

author keywords: FRAPCON; rod internal pressure; IFBA
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Web Of Science, NC State University Libraries
Added: August 6, 2018

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.

UN Sustainable Development Goal Categories
Sources: Web Of Science, NC State University Libraries
Added: August 6, 2018

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.

By: R. Pericas*, K. Ivanov*, F. Reventós* & L. Batet*

author keywords: Nuclear safety; 3D neutron kinetics; Reactor physics modeling; Best Estimate calculation; 3D NK-TH; Dynamic control rod movement
TL;DR: A Best Estimate validation calculation with a coupled thermal–hydraulic and 3D neutron kinetic model for Asco-II Nuclear Power Plant is provided and the developed system models and the code modifications are robust enough to be used for future safety analysis. (via Semantic Scholar)
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2015 journal article

Examination and refinement of fine energy group structure for high temperature reactor analysis

Annals of Nuclear Energy, 80, 279–292.

By: T. Ngeleka*, K. Ivanov* & S. Levine*

author keywords: CPXSD method; HTR; Energy group structure
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: February 24, 2020

2015 journal article

Large-scale Monte Carlo neutron transport calculations with thermal hydraulic feedback

Annals of Nuclear Energy, 84, 204–219.

By: A. Ivanov*, V. Sanchez*, R. Stieglitz* & K. Ivanov*

author keywords: Multiphysics calculations; Monte Carlo transport; Wielandt method; Variance reduction; Stochastic approximation; Convergence acceleration
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
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

2014 journal article

A cycle-specific cross-section update for real-time simulation of VVER-1000 core

Progress in Nuclear Energy, 74, 222–231.

By: E. Georgieva*, Y. Dinkov* & K. Ivanov*

author keywords: VVER; Real-time simulation; Core model; Cross sections
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2014 journal article

ASSESSMENT OF MICROX-2 CODE WITH NEW ENDF/B-VII RELEASE 0 MASTER LIBRARIES

NUCLEAR TECHNOLOGY, 186(3), 305–316.

By: J. Hou*, H. Choi* & K. Ivanov*

author keywords: MICROX-2; cross-section library; ENDF/B-VII
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Web Of Science, NC State University Libraries, ORCID
Added: August 6, 2018

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*

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 Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2014 journal article

Development of an iterative diffusion-transport method based on MICROX-2 cross section libraries

ANNALS OF NUCLEAR ENERGY, 77, 335–342.

By: J. Hou*, H. Choi* & K. Ivanov*

author keywords: 2-D lattice calculation; Iterative Diffusion-Transport method; Cross section generation; Boundary condition
Sources: Web Of Science, NC State University Libraries, ORCID
Added: August 6, 2018

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.

By: A. Ivanov*, V. Sanchez* & K. Ivanov*

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

author keywords: MCNP; SUBCHANFLOW; Monte-Carlo; Criticality; Coupled calculations
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

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.

By: A. Ivanov*, V. Sanchez*, R. Stieglitz* & K. Ivanov*

author keywords: Coupled codes; Stochastic approximation; Internal coupling; MCNP5; SUBCHANFLOW; Collision density estimator
TL;DR: Using multi-processor computer architectures and implementing collision density flux estimator, it is possible to reduce the Monte-Carlo running time and obtain converged results within reasonable time limit and it is shown that large fuel assemblies can be analyzed on subchannel level. (via Semantic Scholar)
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

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.

By: D. Colameco*, B. Ivanov*, D. Beacon* & K. Ivanov*

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

author keywords: NGM; ITDM; Embedded Transport; Partial Currents
TL;DR: This paper presents an update on the development of an advanced methodology for core calculations that uses local heterogeneous solutions for on-the-fly nodal cross-section generation, and focuses on burnup methodology, axial leakage and 3D modeling. (via Semantic Scholar)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

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.

By: S. Ghrayeb*, A. Ougouag*, M. Ouisloumen* & K. Ivanov*

author keywords: Resonance scattering; Multi-group formulation; Doppler effect; Up-scattering; Elastic scattering
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2014 journal article

Self-shielding models of MICROX-2 code: Review and updates

ANNALS OF NUCLEAR ENERGY, 64, 256–263.

By: J. Hou*, H. Choi* & K. Ivanov*

author keywords: MICROX-2; Resonance self-shielding; Dancoff factor
TL;DR: The results have shown that the implementation of the updated self-shielding models is correct and the accuracy of physics calculation is improved, and the prediction error of the infinite multiplication factor of the Monte Carlo code is reduced. (via Semantic Scholar)
Sources: Web Of Science, NC State University Libraries, ORCID
Added: August 6, 2018

2014 journal article

The effect of changing enrichments on core performance

Annals of Nuclear Energy, 75, 139–145.

By: S. Levine*, T. Blyth* & K. Ivanov*

author keywords: Low leakage core; Haling Power Depletion; Burnable poisons; Normalized power; Pin peak power; Fuel costs
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: February 24, 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*

Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2013 journal article

Analysis of the OECD/NRC Oskarshamn-2 BWR stability benchmark

Annals of Nuclear Energy, 67, 4–12.

By: T. Kozlowski*, A. Wysocki*, I. Gajev*, Y. Xu*, T. Downar*, K. Ivanov*, J. Magedanz*, M. Hardgrove* ...

author keywords: Oskarshamn-2; BWR stability; Stability event; TRACE/PARCS; Code validation; Coupled code
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

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.

By: A. Ivanov*, V. Sanchez*, R. Stieglitz* & K. Ivanov*

author keywords: Coupled codes; MCNP5; SUBCHANFLOW; Design; Safety; HPC
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
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
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

Progress in the development of an implicit steady state solution in the coupled code TRACE/PARCS

Progress in Nuclear Energy, 66, 1–12.

By: M. Ellis*, J. Watson* & K. Ivanov*

author keywords: Implicit coupling; TRACE; PARCS; Multiphysics
TL;DR: An evaluation of the CPU runtime required to complete a steady state calculation using the implicit method shows that the well-developed and optimized explicit solution method currently requires less CPU runtime than the implicit solution method which has yet to be optimized. (via Semantic Scholar)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2013 journal article

Understanding using the Haling Power Depletion (HPD) as a guide for designing PWR cores

Annals of Nuclear Energy, 53, 120–128.

By: S. Levine*, T. Blyth* & K. Ivanov*

author keywords: Low leakage core; Haling power depletion; Burnable poisons; Normalized power; Pin peak power
TL;DR: Techniques using the HPD results have been developed to help guide efficiently the placing of BPs in the core for a good solution to produce several excellent low leakage core configurations that are viable for power production. (via Semantic Scholar)
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

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.

By: A. Gomez-Torres*, V. Sanchez-Espinoza*, K. Ivanov* & R. Macian-Juan*

author keywords: Best estimate; High fidelity; Coupled code; Simplified transport; Sub-channel code; Local safety parameters
TL;DR: DYNSUB has successfully been applied to analyze the behaviour of one eight of a PWR core during a REA transient by a pin-by-pin simulation consisting of a huge amount of nodes, validating the correctness of the coupling strategy. (via Semantic Scholar)
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

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.

By: A. Gomez-Torres, V. Sanchez-Espinoza, K. Ivanov* & R. Macian-Juan

TL;DR: The results using FPI are very promising and represent a very good option in order to optimize computational times without losing accuracy, however it is also shown that a FPI scheme can produce inaccurate results if the time step is not chosen in agreement with the analyzed transient. (via Semantic Scholar)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2011 journal article

Deterministic modeling of higher angular moments of resonant neutron scattering

Annals of Nuclear Energy, 38(10), 2291–2297.

By: S. Ghrayeb*, M. Ouisloumen*, A. Ougouag* & K. Ivanov*

author keywords: Deterministic; Resonance scattering; Moment; Kernel; Doppler effect
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2011 journal article

MCOR – Monte Carlo depletion code for reference LWR calculations

Annals of Nuclear Energy, 38(4), 731–741.

By: F. Espel*, C. Tippayakul*, K. Ivanov* & S. Misu*

author keywords: Monte Carlo depletion; MCOR; Fuel assembly reference calculations; MCNP5; KORIGEN
TL;DR: The article describes the capabilities of the MCOR code system; from its design and development to its latest improvements and further ameliorations. (via Semantic Scholar)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2010 journal article

Application of Global Sensitivity Analysis to Nuclear Reactor Calculations

Procedia - Social and Behavioral Sciences, 2(6), 7726–7727.

By: F. Espel*, S. Tarantola*, S. Ghrayeb* & K. Ivanov*

UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2010 journal article

Spectral zone selection methodology for pebble bed reactors

Annals of Nuclear Energy, 38(1), 80–87.

By: R. Mphahlele*, A. Ougouag*, K. Ivanov* & H. Gougar*

author keywords: High temperature gas cooled reactor (HTR); Pebble Bed Modular Reactor (PBMR); Spectral zone; Selection methodology; Optimization algorithm
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2010 journal article

Transport model based on three-dimensional cross-section generation for TRIGA core analysis

Annals of Nuclear Energy, 37(9), 1254–1260.

By: N. Kriangchaiporn, K. Ivanov*, A. Haghighat* & C. Sears*

author keywords: TRIGA; Discrete ordinates; Cross-section generation; Transport calculation; Core analysis; DORT/TORT
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
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
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2009 journal article

Application of TRACE/PARCS to BWR stability analysis

Annals of Nuclear Energy, 36(3), 317–323.

By: Y. Xu*, T. Downar*, R. Walls*, K. Ivanov*, J. Staudenmeier* & J. March-Lueba*

UN Sustainable Development Goal Categories
6. Clean Water and Sanitation (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

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.

By: C. Tippayakul*, K. Ivanov* & C. Frederick Sears

TL;DR: An intermediate verification of the fuel management system was performed to assess the correctness of the newly implemented schemes against HELIOS and the agreement of the predicted core excess reactivities and the measured values is found to be good considering the measurement uncertainties. (via Semantic Scholar)
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2008 journal article

Evaluation of PBMR control rod worth using full three-dimensional deterministic transport methods

Annals of Nuclear Energy, 35(6), 1050–1055.

By: B. Tyobeka*, K. Ivanov* & A. Pautz*

Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2008 journal article

New genetic algorithms (GA) to optimize PWR reactors

Annals of Nuclear Energy, 35(1), 113–120.

By: F. Alim*, K. Ivanov*, S. Yilmaz & S. Levine*

TL;DR: The GARCO–PSU code simultaneously optimizes the core loading pattern (LP) and the burnable poison placement in a pressurized water reactor (PWR) by developing an innovative genetic algorithm (GA). (via Semantic Scholar)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2007 journal article

Accuracy evaluation of pin exposure calculations in current LWR core design codes

Annals of Nuclear Energy, 35(3), 414–424.

By: V. Xulubana*, C. Tippayakul*, K. Ivanov*, S. Levine* & M. Mahgerefteh

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*

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

2007 journal article

New genetic algorithms (GA) to optimize PWR reactors

Annals of Nuclear Energy, 35(1), 93–112.

By: F. Alim*, K. Ivanov* & S. Levine*

TL;DR: The objective of this study was to develop a unique scientific methodology as well as a practical tool for designing the loading pattern (LP) and burnable poison (BP) pattern for a given Pressurized Water Reactor (PWR) core. (via Semantic Scholar)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2007 journal article

New genetic algorithms (GA) to optimize PWR reactors

Annals of Nuclear Energy, 35(1), 121–131.

By: F. Alim*, K. Ivanov* & S. Levine*

UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2007 journal article

The three-dimensional neutron kinetics coupled with thermal-hydraulics in RBMK accident analysis

Nuclear Engineering and Design, 238(4), 1002–1025.

By: F. D’Auria*, S. Soloviev*, V. Malofeev*, K. Ivanov* & C. Parisi*

Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2007 journal article

Utilization of two-dimensional deterministic transport methods for analysis of pebble-bed reactors

Annals of Nuclear Energy, 34(5), 396–405.

By: B. Tyobeka*, K. Ivanov* & A. Pautz

TL;DR: The results show clearly that even in steady-state calculations, the differences between diffusion and transport-based methods in analyzing the PBMR are observed and need to be addressed. (via Semantic Scholar)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2006 journal article

Analysis of the VVER1000 coolant trip benchmark using the coupled RELAP5/PARCS code

Progress in Nuclear Energy, 48(8), 806–819.

By: A. Bousbia Salah*, J. Vedovi*, F. D'Auria*, G. Galassi* & K. Ivanov*

author keywords: coupled code calculations; VVER1000 benchmark; RELAP5/PARCS
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2006 journal article

Application of genetic algorithms to optimize burnable poison placement in pressurized water reactors

Annals of Nuclear Energy, 33(5), 446–456.

By: S. Yilmaz, K. Ivanov*, S. Levine* & M. Mahgerefteh

TL;DR: An efficient and a practical genetic algorithm (GA) tool was developed and applied successfully to Burnable Poison (BP) placement optimization problem in the reference Three Mile Island-1 (TMI-1) core. (via Semantic Scholar)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2006 journal article

Comparative RELAP5-3D analysis in support of the NPP DBA analysis in Ukraine

Progress in Nuclear Energy, 48(8), 891–911.

By: A. Shkarupa*, I. Kadenko, A. Malanich*, A. Kovtonyuk* & K. Ivanov*

author keywords: safety analysis; local reactivity effects; point kinetics; coupled code
TL;DR: The goal of this RELAP5-3D analysis is to examine the differences in results obtained by the three-dimensional approach and the methodology that was used in Ukrainian ISA projects. (via Semantic Scholar)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

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.

By: S. Yilmaz, K. Ivanov*, S. Levine* & M. Mahgerefteh

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*

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 Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

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.

By: B. Ivanov*, S. Aniel*, P. Siltanen*, E. Royer* & K. Ivanov*

author keywords: V1000CT; benchmark; VVER; coupled; cross section; HELIOS
TL;DR: The present paper summarizes the different steps applied to analyze the neutronic codes and their predictions as well as the impact of cross-section generation procedures. (via Semantic Scholar)
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: October 29, 2020

2006 journal article

Introduction to the special issue on the OECD/DOE/CEA V1000CT-1 benchmark

Progress in Nuclear Energy, 48(8), 727.

By: K. Ivanov*

Sources: Crossref, NC State University Libraries
Added: October 29, 2020

2006 journal article

Modeling and optimization of existing beam port facility of PSBR

Annals of Nuclear Energy, 33(17-18), 1391–1395.

By: F. Alim*, K. Bekar*, K. Ivanov*, K. Unlu*, J. Brenizer* & Y. Azmy*

TL;DR: Examining the existing BPs for neutron and gamma outputs and developing a new core-moderator location and BP geometry in PSBR finds some artificial models developed and compared with the original model. (via Semantic Scholar)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

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.

By: B. Ivanov*, K. Ivanov*, E. Royer*, S. Aniel*, U. Bieder*, N. Kolev*, P. Groudev*

author keywords: V1000CT; benchmark; VVER; coupled
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

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.

By: J. Gozalvez*, S. Yilmaz, F. Alim*, K. Ivanov* & S. Levine*

TL;DR: The main objective was to develop NNs models capable of simulating useful reactor physics parameters to filter out the bad designs created in Genetic Algorithms run without the need to perform reactor physics calculations for evaluation of individuals. (via Semantic Scholar)
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

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.

By: N. Kolev*, N. Petrov*, B. Ivanov* & K. Ivanov*

author keywords: best-estimate codes; code assessment; OECD benchmarks; VVER-1000; pump start-up; reactor safety
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

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.

By: F. Reitsma, G. Strydom, J. de Haas, K. Ivanov*, B. Tyobeka*, R. Mphahlele*, T. Downar*, V. Seker* ...

Sources: Crossref, NC State University Libraries
Added: August 28, 2020

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.

By: B. Ivanov*, K. Ivanov* & R. Stamm'ler

author keywords: HELIOS; deterministic; transport; MOX
TL;DR: This paper presents the methodology employed in solving the C5G7 MOX Fuel Assembly Problem using the transport code HELIOS, and describes the seven-group transport-corrected isotropic scattering cross-sections provided. (via Semantic Scholar)
UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2003 journal article

Development of the VVER core loading optimization system

Annals of Nuclear Energy, 31(7), 747–772.

By: C. Guler*, S. Levine*, K. Ivanov*, J. Svarny*, V. Krysl*, P. Mikolas*, J. Sustek*

UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

2003 journal article

Minimizing the gamma radiation effects to spent fuel pool walls

Annals of Nuclear Energy, 31(5), 459–480.

By: C. Tippayakul*, S. Levine*, K. Ivanov* & M. Mahgerefteh

UN Sustainable Development Goal Categories
7. Affordable and Clean Energy (OpenAlex)
Sources: Crossref, NC State University Libraries
Added: August 28, 2020

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