# Publications

The list below contains the last 50 Nuclear Engineering publications.

## Nuclear Engineering

[1]

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.
[2]

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.
[3]

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.
[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]

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.
[6]

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.
[7]

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.
[8]

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.
[9]

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.
[10]

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.
[11]

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.
[12]

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.
[13]

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.
[14]

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.
[15]

K. Johnson

*et al.*, "Oxidation of accident tolerant fuel candidates,"*Journal of Nuclear Science and Technology*, vol. 54, no. 3, pp. 280-286, 2017.
[16]

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.
[17]

T. Schuler

*et al.*, "Transport properties of C and O in UN fuels,"*Physical Review B*, vol. 95, no. 9, 2017.
[18]

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.
[19]

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.
[20]

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.
[21]

[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]

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.
[24]

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.

[25]

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

[26]

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.
[27]

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.
[28]

K. D. Johnson

*et al.*, "Spark plasma sintering and porosity studies of uranium nitride,"*Journal of Nuclear Materials*, vol. 473, pp. 13-17, 2016.
[29]

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.
[30]

A. Claisse

*et al.*, "Transport properties in dilute UN(X) solid solutions (X = Xe, Kr),"*Physical Review B*, vol. 94, no. 17, 2016.
[31]

Z. Chang

*et al.*, "Anomalous bias factors of dislocations in bcc iron,"*Journal of Nuclear Materials*, vol. 461, pp. 221-229, 2015.
[32]

Z. Chang

*et al.*, "Assessment of the dislocation bias in fcc metals and extrapolation to austenitic steels,"*Journal of Nuclear Materials*, vol. 465, 2015.
[33]

[34]

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.
[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]

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

[37]

[38]

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.

[39]

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.
[40]

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.
[41]

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.
[42]

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.

[43]

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.
[44]

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.
[45]

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.
[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]

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.
[48]

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.
[49]

U. Tippawan

*et al.*, "Light-ion Production in 175 MeV Neutron-induced Reactions on Oxygen,"*Nuclear Data Sheets*, vol. 119, pp. 194-196, 2014.
[50]

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.## Reactor Technology

[1]

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.
[2]

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.
[3]

H. Anglart,

*Applied Reactor Technology.*1st ed. Warsaw, Poland : Warsaw University of Technology Publishing House, 2013.
[4]

H. Anglart,
"Dry Patch Formation in Diabatic Annular Two-Phase Flows,"

*Journal of Power Technologies*, vol. 94, pp. 85-95, 2014.
[5]

H. Anglart,
"Modelling of Liquid Film Flow in Annuli,"

*Journal of Power Technologies*, vol. 94, pp. 8-15, 2014.
[6]

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.
[7]

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.
[8]

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.
[9]

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.
[10]

D. Caraghiaur, C. Adamsson and H. Anglart,
"Deposition of Inertial Drops in Eulerian Formulation,"
in

*Proceedings of NURETH-15*, 2013.
[11]

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.
[12]

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.
[13]

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.
[14]

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.
[15]

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.
[16]

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.
[17]

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.
[18]

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.
[19]

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.
[20]

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.
[21]

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.
[22]

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.
[23]

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.
[24]

R. Pegonen

*et al.*, "Hot fuel element thermal-hydraulics in the Jules Horowitz Reactor,"*Nuclear Engineering and Design*, vol. 300, pp. 149-160, 2016.
[25]

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.
[26]

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.
[27]

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, 2017.
[28]

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.
[29]

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.
[30]

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.

[31]

B. Olsen and J. Dufek,
"Fission source sampling in coupled Monte Carlo simulations,"

*Kerntechnik (1987)*, vol. 82, no. 2, pp. 206-209, 2017.
[32]

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.
[33]

S. A. Qvist

*et al.*, "Autonomous Reactivity Control (ARC) - Principles, geometry and design process,"*Nuclear Engineering and Design*, vol. 307, pp. 249-274, 2016.
[34]

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.
[35]

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

[36]

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.
[37]

A. Riber Marklund

*et al.*, "Passive acoustic leak detection for sodium fast reactors using hidden Markov models,"*IEEE Transactions on Nuclear Science*, 2016.
[38]

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.

[39]

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.
[40]

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.
[41]

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.

[42]

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.
[43]

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.
[44]

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.
[45]

[46]

[47]

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.
[48]

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.
[49]