Publications

The list below contains the last 50 Nuclear Engineering publications.

Nuclear Engineering

[1]

N. Castin et al., "Advanced atomistic models for radiation damage in Fe-based alloys : Contributions and future perspectives from artificial neural networks," Computational materials science, vol. 148, pp. 116-130, 2018.

[2]

A. Bakaev et al., "Effect of isotropic stress on dislocation bias factor in bcc iron : an atomistic study," Philosophical Magazine, vol. 98, no. 1, pp. 54-74, 2018.

[3]

C. S. Becquart et al., "A DFT study of the stability of SIAs and small SIA clusters in the vicinity of solute atoms in Fe," Journal of Nuclear Materials, vol. 500, pp. 92-109, 2018.

[4]

S. Middleburgh et al., "Solution of hydrogen in accident tolerant fuel candidate material : U3Si2," Journal of Nuclear Materials, vol. 501, pp. 234-237, 2018.

[5]

T. Schuler et al., "Transport properties of C and O in UN fuels," Physical Review B, vol. 95, no. 9, 2017.

[6]

L. Messina et al., "Introducing ab initio based neural networks for transition-rate prediction in kinetic Monte Carlo simulations," Physical Review B, vol. 95, no. 6, 2017.

[7]

N. Castin et al., "Improved atomistic Monte Carlo models based on ab-initio -trained neural networks : Application to FeCu and FeCr alloys," Physical Review B, vol. 95, no. 21, 2017.

[8]

G. Bonny et al., "Density functional theory-based cluster expansion to simulate thermal annealing in FeCrW alloys," Philosophical Magazine, vol. 97, no. 5, pp. 299-317, 2017.

[9]

K. Johnson et al., "Oxidation of accident tolerant fuel candidates," Journal of Nuclear Science and Technology, vol. 54, no. 3, pp. 280-286, 2017.

[10]

G. Bonny et al., "Interatomic potential to study the formation of NiCr clusters in high Cr ferritic steels," Journal of Nuclear Materials, vol. 484, pp. 42-50, 2017.

[11]

E. Bubelis et al., "System codes benchmarking on a low sodium void effect SFR heterogeneous core under ULOF conditions," Nuclear Engineering and Design, vol. 320, pp. 325-345, 2017.

[12]

M. Chiapetto et al., "Nanostructure evolution of neutron-irradiated reactor pressure vessel steels: Revised Object kinetic Monte Carlo model," Nuclear Instruments and Methods in Physics Research Section B : Beam Interactions with Materials and Atoms, vol. 393, pp. 105-109, 2017.

[13]

D. J. M. King et al., "DFT study of the hexagonal high-entropy alloy fission product system," Journal of Nuclear Materials, vol. 488, pp. 70-74, 2017.

[14]

K. D. Johnson et al., "Spark plasma sintering and porosity studies of uranium nitride," Journal of Nuclear Materials, vol. 473, pp. 13-17, 2016.

[15]

K. D. Johnson, "High Performance Fuels for Water-Cooled Reactor Systems," Doctoral thesis Stockholm, Sweden : KTH Royal Institute of Technology, TRITA-FYS, 2016:72, 2016.

[16]

D. A. Lopes, A. Claisse and P. Olsson, "Ab-initio study of C and O impurities in uranium nitride," Journal of Nuclear Materials, vol. 478, pp. 112-118, 2016.

[17]

L. Messina et al., "Systematic electronic-structure investigation of substitutional impurity diffusion and flux coupling in bcc iron," Physical Review B, vol. 93, no. 18, 2016.

[18]

A. Claisse, "Multiscale modeling of nitride fuels," Doctoral thesis Stockholm : KTH Royal Institute of Technology, TRITA-FYS, 73, 2016.

[19]

A. Claisse et al., "Transport properties in dilute UN(X) solid solutions (X = Xe, Kr)," Physical Review B, vol. 94, no. 17, 2016.

[20]

J. E. Hoogenboom and J. Dufek, "Optimised Iteration in Coupled Monte Carlo - Thermal-Hydraulics Calculations," in SNA + MC 2013 - JOINT INTERNATIONAL CONFERENCE ON SUPERCOMPUTING IN NUCLEAR APPLICATIONS + MONTE CARLO, 2016.

[21]

S. Uygur, "Degradation mechanisms of UN and UN–10U3Si2 pellets of varying microstructure by comparative steam oxidation experiments," , 2016.

[22]

K. D. Johnson et al., "Fabrication and microstructural analysis of UN-U3Si2 composites for accident tolerant fuel applications," Journal of Nuclear Materials, vol. 477, pp. 18-23, 2016.

[23]

L. Messina et al., "An object kinetic Monte Carlo model for the microstructure evolution of neutron-irradiated reactor pressure vessel steels," Physica Status Solidi (a) applications and materials science, vol. 213, no. 11, pp. 2974-2980, 2016.

[24]

P. Olsson, C. S. Becquart and C. Domain, "Ab initio threshold displacement energies in iron," Materials Research Letters, vol. 4, no. 4, pp. 219-225, 2016.

[25]

A. De Backer et al., "Primary damage in tungsten using the binary collision approximation, molecular dynamic simulations and the density functional theory," Physica Scripta, vol. T167, 2016.

[26]

A. Claisse et al., "GGA plus U study of uranium mononitride : A comparison of the U-ramping and occupation matrix schemes and incorporation energies of fission products," Journal of Nuclear Materials, vol. 478, pp. 119-124, 2016.

[27]

K. Lambrinou et al., "Corrosion-resistant ternary carbides for use in heavy liquid metal coolants," in Ceramic Engineering and Science Proceedings, 2016, pp. 19-34.

[28]

E. Suvdantsetseg, S. Qvist and E. Greenspan, "Preliminary transient analysis of the Autonomous Reactivity Control system for fast reactors," Annals of Nuclear Energy, vol. 77, pp. 47-64, 2015.

[29]

Z. Chang et al., "Assessment of the dislocation bias in fcc metals and extrapolation to austenitic steels," Journal of Nuclear Materials, vol. 465, 2015.

[30]

Z. Chang, "Multiscale modelling of radiation-enhanced diffusion phenomena in metals," Doctoral thesis Stockholm : KTH Royal Institute of Technology, TRITA-FYS, 2015:16, 2015.

[31]

A. Claisse and P. Van Uffelen, "Towards the inclusion of open fabrication porosity in a fission gas release model," Journal of Nuclear Materials, vol. 466, pp. 351-356, 2015.

[32]

J. Neuhausen et al., "Properties of irradiated LBE and Pb," in Handbook on Lead-bismuth Eutectic Alloy and Lead Properties, Materials Compatibility, Thermal-hydraulics and Technologies - 2015 Edition (NEA-7268), Fazio, Concetta Ed., : Nuclear Energy Agency of the OECD (NEA), 2015.

[33]

A. M. Raftery, "Fabrication and Characterization of UN-USi_x Nuclear Fuel," , 2015.

[34]

P. Malkki, "The manufacturing of uranium nitride for possible use in light water reactors," Licentiate thesis Stockholm : KTH Royal Institute of Technology, TRITA-FYS, 2015:25, 2015.

[35]

L. Messina, "Multiscale modeling of atomic transport phenomena in ferritic steels," Doctoral thesis Stockholm : KTH Royal Institute of Technology, TRITA-FYS, 2015:80, 2015.

[36]

C. Roedl et al., "Wurtzite silicon as a potential absorber in photovoltaics : Tailoring the optical absorption by applying strain," Physical Review B. Condensed Matter and Materials Physics, vol. 92, no. 4, 2015.

[37]

J. Arnesson, "Numerical Modeling of Radioactive Release Implemented for Loss of Coolant Accident, Evaluated using Latin Hypercube Sampling," , 2015.

[38]

Z. Chang et al., "Anomalous bias factors of dislocations in bcc iron," Journal of Nuclear Materials, vol. 461, pp. 221-229, 2015.

[39]

A. Claisse, "Open porosity fission gas release model applied to nuclear fuels," Licentiate thesis Stockholm : KTH Royal Institute of Technology, TRITA-FYS, 2015:27, 2015.

[40]

L. Messina, L. Malerba and P. Olsson, "Stability and mobility of small vacancy-solute complexes in Fe-MnNi and dilute Fe-X alloys : A kinetic Monte Carlo study," Nuclear Instruments and Methods in Physics Research Section B : Beam Interactions with Materials and Atoms, vol. 352, pp. 61-66, 2015.

[41]

P. R. Hania et al., "Irradiation and post-irradiation examination of uranium-free nitride fuel," Journal of Nuclear Materials, vol. 466, pp. 597-605, 2015.

[42]

S. Bortot, E. Suvdantsetseg and J. Wallenius, "BELLA : a multi-point dynamics code for safety-informed design of fast reactors," Annals of Nuclear Energy, vol. 85, pp. 228-235, 2015.

[43]

N. Sandberg et al., "Modeling of the magnetic free energy of self-diffusion in bcc Fe," Physical Review B. Condensed Matter and Materials Physics, vol. 92, no. 18, 2015.

[44]

J. Ejenstam et al., "Microstructural stability of Fe–Cr–Al alloys at 450–550 °C," Journal of Nuclear Materials, vol. 457, pp. 291-297, 2015.

[45]

P. Malkki et al., "Manufacture of fully dense uranium nitride pellets using hydride derived powders with spark plasma sintering," Journal of Nuclear Materials, vol. 452, no. 1-3, pp. 548-551, 2014.

[46]

K. Tuttelberg and J. Dufek, "Estimation of errors in the cumulative Monte Carlo fission source," Annals of Nuclear Energy, vol. 72, pp. 151-155, 2014.

[47]

E. Suvdantsetseg and J. Wallenius, "An assessment of prompt neutron reproduction time in a reflector dominated fast critical system : ELECTRA," Annals of Nuclear Energy, vol. 71, pp. 159-165, 2014.

[48]

U. Tippawan et al., "Light-ion Production in 175 MeV Neutron-induced Reactions on Oxygen," Nuclear Data Sheets, vol. 119, pp. 194-196, 2014.

[49]

L. Messina et al., "Exact ab initio transport coefficients in bcc Fe-X (X=Cr, Cu, Mn, Ni, P, Si) dilute alloys," Physical Review B. Condensed Matter and Materials Physics, vol. 90, no. 10, pp. 104203, 2014.

[50]

J. B. Piochaud et al., "First-principles study of point defects in an fcc Fe-10Ni-20Cr model alloy," Physical Review B. Condensed Matter and Materials Physics, vol. 89, no. 2, pp. 024101, 2014.

Reactor Technology

[1]

B. Olsen and J. Dufek, "Fission source sampling in coupled Monte Carlo simulations," Kerntechnik (1987), vol. 82, no. 2, pp. 206-209, 2017.

[2]

B. Olsen and J. Dufek, "Stabilization effect of fission source in coupled Monte Carlo simulations," Nuclear engineering and technology : an international journal of the Korean Nuclear Society, vol. 49, no. 5, pp. 1095-1099, 2017.

[3]

R. Pegonen, "Development of an Improved Thermal-Hydraulic Modeling of the Jules Horowitz Reactor," Doctoral thesis Stockholm : KTH Royal Institute of Technology, TRITA-FYS, 2017:01, 2017.

[4]

H. Li and H. Anglart, "CFD prediction of droplet deposition in steam-water annular flow with flow obstacle effects," Nuclear Engineering and Design, vol. 321, pp. 173-179, 2017.

[5]

M. Bergagio, R. Thiele and H. Anglart, "Analysis of temperature fluctuations caused by mixing of non-isothermal water streams at elevated pressure," International Journal of Heat and Mass Transfer, vol. 104, pp. 979-992, 2017.

[6]

R. Pegonen et al., "An improved thermal-hydraulic modeling of the Jules Horowitz Reactor using the CATHARE2 system code," Nuclear Engineering and Design, vol. 311, pp. 156-166, 2017.

[7]

A. Riber Marklund, H. Anglart and F. Michel, "Demonstration of an improved passive acoustic fault detection method on recordings from the Phénix steam generator operating at full power," Annals of Nuclear Energy, vol. 101, pp. 1-14, 2017.

[8]

M. Bergagio and H. Anglart, "Experimental investigation of mixing of non-isothermal water streams at BWR operating conditions," Nuclear Engineering and Design, vol. 317, pp. 158-176, 2017.

[9]

S. A. Qvist et al., "Autonomous Reactivity Control (ARC) - Principles, geometry and design process," Nuclear Engineering and Design, vol. 307, pp. 249-274, 2016.

[10]

M. Tesinsky, J. Wäng and U. Bredolt, "Validation of the hem and moody critical flow models in polca-T," in Physics of Reactors 2016, PHYSOR 2016 : Unifying Theory and Experiments in the 21st Century, 2016, pp. 2724-2732.

[11]

A. Riber Marklund et al., "Passive acoustic leak detection for sodium fast reactors using hidden Markov models," IEEE Transactions on Nuclear Science, 2016.

[12]

M. Bergagio, "Experimental analysis of thermal mixing at reactor conditions," Licentiate thesis : KTH Royal Institute of Technology, TRITA-FYS, 2016:74, 2016.

[13]

J. Dufek and G. Holst, "Correlation of errors in the Monte Carlo fission source and the fission matrix fundamental-mode eigenvector," Annals of Nuclear Energy, vol. 94, pp. 415-421, 2016.

[14]

[15]

A. Riber Marklund, "Passive acoustic leak detection in energy conversion systems of sodium fast reactors," Doctoral thesis : Kungliga Tekniska högskolan, TRITA-FYS, 2016-79, 2016.

[16]

R. Pegonen et al., "Hydraulic modeling of the Jules Horowitz Reactor: Mass flow split between 36 fuel elements," Nuclear Engineering and Design, vol. 308, pp. 9-19, 2016.

[17]

R. Pegonen et al., "Hot fuel element thermal-hydraulics in the Jules Horowitz Reactor," Nuclear Engineering and Design, vol. 300, pp. 149-160, 2016.

[18]

H. Li and H. Anglart, "Prediction of dryout and post-dryout heat transfer using a two-phase CFD model," International Journal of Heat and Mass Transfer, vol. 99, pp. 839-850, 2016.

[19]

H. Li and H. Anglart, "Modeling of annular two-phase flow using a unified CFD approach," Nuclear Engineering and Design, vol. 303, pp. 17-24, 2016.

[20]

A. R. Marklund et al., "Passive acoustic leak detection for sodium cooled fast reactors using hidden Markov models," in 2015 4th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications, ANIMMA 2015, 2015.

[21]

K. Luszczek, "Validation and Benchmarking of Westinghouse BWR lattice physics methods," , 2015.

[22]

K. Tuttelberg and J. Dufek, "Neutron batch size optimisation methodology for Monte Carlo criticality calculations," Annals of Nuclear Energy, vol. 75, pp. 620-626, 2015.

[23]

J. Kotchoubey, "POLCA-T Neutron Kinetics Model Benchmarking," , 2015.

[24]

R. Thiele, "Mechanistic Modeling of Wall-Fluid Thermal Interactions for Innovative Nuclear Systems," Doctoral thesis Stockholm : KTH Royal Institute of Technology, TRITA-FYS, 2015:70, 2015.

[25]

A. Riber Marklund and F. Michel, "Application of a new passive acoustic leak detection approach to recordings from the Dounreay prototype fast reactor," Annals of Nuclear Energy, vol. 85, pp. 175-182, 2015.

[26]

I. Mickus, J. Dufek and K. Tuttelberg, "PERFORMANCE OF THE EXPLICIT EULER AND PREDICTOR-CORRECTOR-BASED COUPLING SCHEMES IN MONTE CARLO BURNUP CALCULATIONS OF FAST REACTORS," Nuclear Technology, vol. 191, no. 2, pp. 193-198, 2015.

[27]

I. Mickus et al., "Development of tall-3d test matrix for APROS code validation," in International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 2015, pp. 4562-4575.

[28]

R. Pegonen et al., "Hot Fuel Element Thermal-Hydraulic Modeling in the Jules Horowitz Reactor Nominal and LOFA Conditions," in Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), 2015.

[29]

H. Anglart et al., "Measurement of Wall Temperature Fluctuations during Thermal Mixing of Non-isothermal Water Streams," in Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), 2015.

[30]

M. Bergagio et al., "Instrumentation for Temperature and Heat Flux Measurement on a Solid Surface under BWR Operating Conditions," in Proceedings of the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16), 2015, pp. 5962-5975.

[31]

M. Gradecka, R. Thiele and H. Anglart, "CFD Investigation of Supercritical Water Flow and Heat Transfer in a Rod Bundle with Grid Spacers," in Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors ISSCWR-7, 2015.

[32]

H. Li and H. Anglart, "CFD model of diabatic annular two-phase flow using the Eulerian-Lagrangian approach," Annals of Nuclear Energy, vol. 77, pp. 415-424, 2015.

[33]

A. Riber Marklund and J. Dufek, "Development and comparison of spectral methods for passive acoustic anomaly detection in nuclear power plants," Applied Acoustics, vol. 83, pp. 100-107, 2014.

[34]

D. Bourgin, "Lattice physics mesh refinement study and its impact on full core nodal simulation results ," , 2014.

[35]

J. Dufek and J. Eduard Hoogenboom, "Description of a stable scheme for steady-state coupled Monte Carlo-thermal-hydraulic calculations," Annals of Nuclear Energy, vol. 68, pp. 1-3, 2014.

[36]

R. Thiele and H. Anglart, "Optimisation of the Flow Path in a Conceptual Pool Type Reactor under Natural Circulation with Lead Coolant," in Proceedings of the NUTHOS-10, 2014.

[37]

H. Anglart, "Modelling of Liquid Film Flow in Annuli," Journal of Power Technologies, vol. 94, pp. 8-15, 2014.

[38]

H. Anglart, "Dry Patch Formation in Diabatic Annular Two-Phase Flows," Journal of Power Technologies, vol. 94, pp. 85-95, 2014.

[39]

I. Anghel and H. Anglart, "On post-dryout heat transfer in channels with flow obstacles," Nuclear Engineering and Design, vol. 270, pp. 351-358, 2014.

[40]

R. Pegonen et al., "Investigation of Thermal Mixing in the Control Rod Top Tube Using Large Eddy Simulation," Journal of Power Technologies, vol. 94, no. 1, pp. 67-78, 2014.

[41]

I. Anghel and H. Anglart, "Wall Temperature Prediction in Annular Geometry during Post-Dryout Heat Transfer," Journal of Power Technologies, vol. 94, pp. 1-7, 2014.

[42]

R. Pegonen et al., "A review of the current thermal-hydraulic modeling of the Jules Horowitz Reactor : A loss of flow accident analysis," Nuclear Engineering and Design, vol. 280, pp. 294-304, 2014.

[43]

J. Olagnon, "Analysis of a new integrator for finite element code for the calculation of fuel rod thermal-mechanical behaviour: MFRONT," , 2013.

[44]

H. Anglart, Applied Reactor Technology. 1st ed. Warsaw, Poland : Warsaw University of Technology Publishing House, 2013.

[45]

M. Jaromin and H. Anglart, "A numerical study of heat transfer to supercritical water flowing upward in vertical tubes under normal and deteriorated conditions," Nuclear Engineering and Design, vol. 264, pp. 61-70, 2013.

[46]

D. Caraghiaur, C. Adamsson and H. Anglart, "Deposition of Inertial Drops in Eulerian Formulation," in Proceedings of NURETH-15, 2013.

[47]

D. Caraghiaur, C. Adamsson and H. Anglart, "A model for inertial drop deposition suitable to predict obstacle effect," Nuclear Engineering and Design, vol. 260, pp. 121-133, 2013.

[48]

M. Jaromin and H. Anglart, "A Numerical Study of the Turbulent Prandtl Number Impact on Heat Transfer to Supercritical Water Flowing Upward Under Deteriorated Conditions," in NURETH-15, 2013.

[49]

J. Dufek and H. Anglart, "Derivation of a stable coupling scheme for Monte Carlo burnup calculations with the thermal-hydraulic feedback," Annals of Nuclear Energy, vol. 62, pp. 260-263, 2013.

[50]

D. Caraghiaur and H. Anglart, "Drop deposition in annular two-phase flow calculated with Lagrangian Particle Tracking," Nuclear Engineering and Design, vol. 265, pp. 856-866, 2013.