Works (80)

Updated: March 28th, 2024 15:26

2023 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

co-author countries: United States of America 🇺🇸
author keywords: Monte Carlo; Hybrid neutronics method; Diffusion synthetic acceleration
Sources: ORCID, Web Of Science
Added: December 23, 2022

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.

By: C. Vaglio-Gaudard*, C. Destouches*, A. Hawari n, M. Avramova n, K. Ivanov n, T. Valentine*, P. Blaise*, J. Hudelot*

co-author countries: France 🇫🇷 United States of America 🇺🇸
author keywords: multi-physics; high-fidelity; coupling; validation; experiment; research reactors; reactivity feedback effects
Sources: Web Of Science, ORCID
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

co-author countries: United States of America 🇺🇸
author keywords: CTF; Sodium fast reactors; Multi-physics; Hi2Lo
Sources: Web Of Science, ORCID
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

co-author countries: United States of America 🇺🇸
author keywords: fuel performance; uncertainty quantification (UQ); sensitivity analysis (SA); aleatoric uncertainty; epistemic uncertainty; pellet cladding mechanical interaction (PCMI)
Sources: Web Of Science, ORCID
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

co-author countries: United States of America 🇺🇸 South Africa 🇿🇦
author keywords: Uncertainty quantification; Deep neural networks; Bayesian Neural Networks; Monte Carlo dropout
Sources: ORCID, Web Of Science
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.

co-author countries: United States of America 🇺🇸
Sources: Web Of Science, ORCID
Added: March 27, 2023

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

co-author countries: United States of America 🇺🇸
author keywords: multi-physics; CTF; PARCS; LWR; uncertainty quantification
Sources: Web Of Science, 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*

co-author countries: United States of America 🇺🇸
author keywords: Nodal Expansion Method (NEM); Adjoint Lagrange Multiplier; Axial Offset (AO); Perturbation analysis; Sensitivity analysis; IAEA
Sources: Web Of Science, ORCID
Added: May 30, 2023

2022 journal article

Propagation of VHTRC manufacturing uncertainties with RAVEN/PHISICS

ANNALS OF NUCLEAR ENERGY, 165.

co-author countries: United States of America 🇺🇸
author keywords: PHISICS; RAVEN; VHTRC; Manufacturing Uncertainties; Monte Carlo Sampling
Sources: Web Of Science, ORCID
Added: November 8, 2021

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

co-author countries: Germany 🇩🇪 United States of America 🇺🇸
author keywords: Nodal Expansion Method (NEM); Lagrange multiplier; Adjoint; Diffusion equation; Verification; Perturbation analysis; Sensitivity analysis; IAEA-3D benchmark
Sources: Web Of Science, ORCID
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

co-author countries: France 🇫🇷 United States of America 🇺🇸
author keywords: Multi-physics modeling; Validation and uncertainty quantification; UAM-LWR; Data assimilation
Sources: Web Of Science, ORCID
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

co-author countries: United States of America 🇺🇸
author keywords: transport-corrected SP3; nodal expansion method; generalized equivalence theory; discontinuity factors
Sources: Web Of Science, ORCID
Added: October 11, 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

co-author countries: United States of America 🇺🇸
author keywords: LWR; Uncertainty analysis; Benchmark; Neutronics; Summary
Sources: Web Of Science, ORCID
Added: October 1, 2021

2020 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*

co-author countries: United States of America 🇺🇸
author keywords: PHISICS; NEWT; High Temperature Gas-cooled Reactors; Group structure; Adaptive sampling; RAVEN
Sources: Web Of Science, ORCID
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

co-author countries: United States of America 🇺🇸 South Africa 🇿🇦
Sources: Web Of Science, ORCID
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*

co-author countries: France 🇫🇷 United States of America 🇺🇸
Sources: Web Of Science, ORCID
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*

co-author countries: United States of America 🇺🇸
author keywords: Uncertainty quantification; stochastic sampling; PWR; rod ejection accident; multiphysics simulation
Sources: Crossref, 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.

co-author countries: United States of America 🇺🇸
author keywords: PHISICS/RELAP5-3D; TRITON/NEWT; High Temperature Gas-cooled Reactors; Neutron flux spectrum; Super cells; Cross section libraries; Power density
Sources: Crossref, ORCID
Added: February 24, 2020

2017 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

co-author countries: Bulgaria 🇧🇬 United States of America 🇺🇸
Sources: Web Of Science, ORCID
Added: August 6, 2018

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*

co-author countries: Spain 🇪🇸 United States of America 🇺🇸
author keywords: Safety analysis; coupled NK-TH; best-estimate plus uncertainty
Sources: Crossref, ORCID
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

co-author countries: United States of America 🇺🇸
author keywords: Low leakage core; Haling power depletion; Burnable poisons; Peak pin power; Fuel cost
Sources: Crossref, ORCID
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*

co-author countries: Russian Federation 🇷🇺 United States of America 🇺🇸
author keywords: Neutron transients; Space-time benchmark C5G7-TD; Kinetics parameters
Sources: Web Of Science, ORCID
Added: August 6, 2018

2017 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

co-author countries: United States of America 🇺🇸
author keywords: FRAPCON; rod internal pressure; IFBA
Sources: Web Of Science, 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

co-author countries: United States of America 🇺🇸
author keywords: SP3; MOX; Nodal expansion method; Neutron diffusion; Transverse leakage
Sources: Web Of Science, ORCID
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*

co-author countries: Bulgaria 🇧🇬 Germany 🇩🇪 United States of America 🇺🇸
Sources: NC State University Libraries, ORCID
Added: August 6, 2018

2016 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*

co-author countries: Spain 🇪🇸 United States of America 🇺🇸
author keywords: Nuclear safety; 3D neutron kinetics; Reactor physics modeling; Best Estimate calculation; 3D NK-TH; Dynamic control rod movement
Sources: Crossref, ORCID
Added: August 28, 2020

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

co-author countries: United States of America 🇺🇸
author keywords: MCNP6; CTF; Internal coupling; Relaxation acceleration
Sources: Web Of Science, ORCID
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.

co-author countries: Austria 🇦🇹 United States of America 🇺🇸
Sources: Web Of Science, ORCID
Added: August 6, 2018

2015 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*

co-author countries: United States of America 🇺🇸
author keywords: 2-D lattice calculation; Iterative Diffusion-Transport method; Cross section generation; Boundary condition
Sources: Web Of Science, ORCID
Added: August 6, 2018

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*

co-author countries: United States of America 🇺🇸 South Africa 🇿🇦
author keywords: CPXSD method; HTR; Energy group structure
Sources: Crossref, ORCID
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*

co-author countries: Germany 🇩🇪 United States of America 🇺🇸
author keywords: Multiphysics calculations; Monte Carlo transport; Wielandt method; Variance reduction; Stochastic approximation; Convergence acceleration
Sources: Crossref, ORCID
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*

co-author countries: Germany 🇩🇪 France 🇫🇷 United States of America 🇺🇸
author keywords: Benchmark; Uncertainty; Multi-physics; Multi-scale
Sources: Crossref, ORCID
Added: February 24, 2020

2015 journal article

The effect of changing enrichments on core performance

Annals of Nuclear Energy, 75, 139–145.

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

co-author countries: United States of America 🇺🇸
author keywords: Low leakage core; Haling Power Depletion; Burnable poisons; Normalized power; Pin peak power; Fuel costs
Sources: Crossref, ORCID
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*

co-author countries: Bulgaria 🇧🇬 United States of America 🇺🇸
author keywords: VVER; Real-time simulation; Core model; Cross sections
Sources: Crossref, ORCID
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*

co-author countries: United States of America 🇺🇸
author keywords: MICROX-2; cross-section library; ENDF/B-VII
Sources: Web Of Science, ORCID
Added: August 6, 2018

2014 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* ...

co-author countries: Sweden 🇸🇪 United States of America 🇺🇸
author keywords: Oskarshamn-2; BWR stability; Stability event; TRACE/PARCS; Code validation; Coupled code
Sources: Crossref, ORCID
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*

co-author countries: United States of America 🇺🇸 South Africa 🇿🇦
Sources: Crossref, ORCID
Added: August 28, 2020

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*

co-author countries: Germany 🇩🇪 United States of America 🇺🇸

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
Sources: Crossref, ORCID
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*

co-author countries: Germany 🇩🇪 United States of America 🇺🇸
author keywords: Coupled codes; Stochastic approximation; Internal coupling; MCNP5; SUBCHANFLOW; Collision density estimator
Sources: Crossref, ORCID
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*

co-author countries: United States of America 🇺🇸

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
Sources: Crossref, ORCID
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*

co-author countries: United States of America 🇺🇸
author keywords: Resonance scattering; Multi-group formulation; Doppler effect; Up-scattering; Elastic scattering
Sources: Crossref, ORCID
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*

co-author countries: United States of America 🇺🇸
author keywords: MICROX-2; Resonance self-shielding; Dancoff factor
Sources: Web Of Science, ORCID
Added: August 6, 2018

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*

co-author countries: United States of America 🇺🇸
Sources: Crossref, ORCID
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*

co-author countries: Germany 🇩🇪 United States of America 🇺🇸
author keywords: Coupled codes; MCNP5; SUBCHANFLOW; Design; Safety; HPC
Sources: Crossref, ORCID
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

co-author countries: United States of America 🇺🇸
author keywords: MCNP5; COBRA-TF; NEM; NJOY; Coupled calculations; BWR
Sources: Crossref, ORCID
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*

co-author countries: United States of America 🇺🇸
author keywords: Implicit coupling; TRACE; PARCS; Multiphysics
Sources: Crossref, ORCID
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*

co-author countries: United States of America 🇺🇸
author keywords: Low leakage core; Haling power depletion; Burnable poisons; Normalized power; Pin peak power
Sources: Crossref, ORCID
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*

co-author countries: Germany 🇩🇪
author keywords: Best estimate; High fidelity; Coupled code; Simplified transport; Sub-channel code; Local safety parameters
Sources: Crossref, ORCID
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

Sources: Crossref, ORCID
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*

co-author countries: United States of America 🇺🇸
author keywords: Deterministic; Resonance scattering; Moment; Kernel; Doppler effect
Sources: Crossref, ORCID
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

co-author countries: United States of America 🇺🇸
author keywords: Monte Carlo depletion; MCOR; Fuel assembly reference calculations; MCNP5; KORIGEN
Sources: Crossref, ORCID
Added: August 28, 2020

2011 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*

co-author countries: United States of America 🇺🇸
author keywords: High temperature gas cooled reactor (HTR); Pebble Bed Modular Reactor (PBMR); Spectral zone; Selection methodology; Optimization algorithm
Sources: Crossref, ORCID
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*

co-author countries: Italy 🇮🇹 United States of America 🇺🇸
Sources: Crossref, ORCID
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*

co-author countries: United States of America 🇺🇸
author keywords: TRIGA; Discrete ordinates; Cross-section generation; Transport calculation; Core analysis; DORT/TORT
Sources: Crossref, ORCID
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*

co-author countries: United States of America 🇺🇸
author keywords: Verification; Validation; Uncertainty; Design; Analysis
Sources: Crossref, ORCID
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*

co-author countries: United States of America 🇺🇸
Sources: Crossref, ORCID
Added: August 28, 2020

2008 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, ORCID
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

Sources: Crossref, ORCID
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*

co-author countries: Germany 🇩🇪 United States of America 🇺🇸
Sources: Crossref, ORCID
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*

co-author countries: United States of America 🇺🇸
Sources: Crossref, ORCID
Added: August 28, 2020

2008 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*

co-author countries: United States of America 🇺🇸
Sources: Crossref, ORCID
Added: August 28, 2020

2008 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*

co-author countries: United States of America 🇺🇸
Sources: Crossref, ORCID
Added: August 28, 2020

2008 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*

co-author countries: Italy 🇮🇹 Russian Federation 🇷🇺 United States of America 🇺🇸
Sources: Crossref, ORCID
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*

co-author countries: United States of America 🇺🇸
Sources: Crossref, ORCID
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

co-author countries: United States of America 🇺🇸
Sources: Crossref, ORCID
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*

co-author countries: Italy 🇮🇹 United States of America 🇺🇸
author keywords: coupled code calculations; VVER1000 benchmark; RELAP5/PARCS
Sources: Crossref, ORCID
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

co-author countries: United States of America 🇺🇸
Sources: Crossref, ORCID
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*

co-author countries: Ukraine 🇺🇦 United States of America 🇺🇸
author keywords: safety analysis; local reactivity effects; point kinetics; coupled code
Sources: Crossref, ORCID
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

co-author countries: United States of America 🇺🇸
Sources: Crossref, ORCID
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*

co-author countries: Spain 🇪🇸 United States of America 🇺🇸
Sources: Crossref, ORCID
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*

co-author countries: Finland 🇫🇮 France 🇫🇷 United States of America 🇺🇸
author keywords: V1000CT; benchmark; VVER; coupled; cross section; HELIOS
Sources: Crossref, ORCID
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, ORCID
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*

co-author countries: United States of America 🇺🇸
Sources: Crossref, ORCID
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*

co-author countries: Bulgaria 🇧🇬 France 🇫🇷 United States of America 🇺🇸
author keywords: V1000CT; benchmark; VVER; coupled
Sources: Crossref, ORCID
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*

co-author countries: Spain 🇪🇸 United States of America 🇺🇸
Sources: Crossref, ORCID
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*

co-author countries: Bulgaria 🇧🇬 United States of America 🇺🇸
author keywords: best-estimate codes; code assessment; OECD benchmarks; VVER-1000; pump start-up; reactor safety
Sources: Crossref, ORCID
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* ...

co-author countries: Netherlands 🇳🇱 United States of America 🇺🇸
Sources: Crossref, ORCID
Added: August 28, 2020

2004 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*

co-author countries: Czechia 🇨🇿 United States of America 🇺🇸
Sources: Crossref, ORCID
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

co-author countries: United States of America 🇺🇸
author keywords: HELIOS; deterministic; transport; MOX
Sources: Crossref, ORCID
Added: August 28, 2020

2004 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

co-author countries: United States of America 🇺🇸
Sources: Crossref, ORCID
Added: August 28, 2020

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