Publications

The list below contains the last 50 Nuclear Engineering publications.

Nuclear Engineering

[1]
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.
[2]
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.
[3]
U. Tippawan et al., "Light-ion Production in 175 MeV Neutron-induced Reactions on Oxygen," Nuclear Data Sheets, vol. 119, pp. 194-196, 2014.
[4]
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.
[5]
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.
[6]
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.
[7]
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.
[8]
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.
[9]
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.
[10]
S. Middleburgh et al., "Solution of hydrogen in accident tolerant fuel candidate material : U3Si2," Journal of Nuclear Materials, vol. 501, pp. 234-237, 2018.
[11]
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.
[12]
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.
[13]
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.
[14]
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.
[15]
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.
[18]
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.
[19]
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.
[20]
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.
[21]
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.
[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]
Z. Chang et al., "Anomalous bias factors of dislocations in bcc iron," Journal of Nuclear Materials, vol. 461, pp. 221-229, 2015.
[25]
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.
[26]
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.
[28]
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.
[29]
A. Claisse et al., "Transport properties in dilute UN(X) solid solutions (X = Xe, Kr)," Physical Review B, vol. 94, no. 17, 2016.
[30]
L. Messina, "Multiscale modeling of atomic transport phenomena in ferritic steels," Doctoral thesis Stockholm : KTH Royal Institute of Technology, TRITA-FYS, 2015:80, 2015.
[31]
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.
[32]
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.
[33]
A. Claisse, "Multiscale modeling of nitride fuels," Doctoral thesis Stockholm : KTH Royal Institute of Technology, TRITA-FYS, 73, 2016.
[36]
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.
[37]
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.
[38]
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.
[39]
K. Johnson et al., "Oxidation of accident tolerant fuel candidates," Journal of Nuclear Science and Technology, vol. 54, no. 3, pp. 280-286, 2017.
[40]
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.
[41]
Z. Chang, "Multiscale modelling of radiation-enhanced diffusion phenomena in metals," Doctoral thesis Stockholm : KTH Royal Institute of Technology, TRITA-FYS, 2015:16, 2015.
[43]
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.
[46]
T. Schuler et al., "Transport properties of C and O in UN fuels," Physical Review B, vol. 95, no. 9, 2017.
[47]
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.
[48]
K. D. Johnson et al., "Spark plasma sintering and porosity studies of uranium nitride," Journal of Nuclear Materials, vol. 473, pp. 13-17, 2016.
[49]
Z. Chang et al., "Assessment of the dislocation bias in fcc metals and extrapolation to austenitic steels," Journal of Nuclear Materials, vol. 465, 2015.
[50]
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.

Reactor Technology

[1]
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.
[2]
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.
[3]
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.
[4]
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.
[6]
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.
[7]
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.
[8]
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.
[9]
H. Anglart, "Dry Patch Formation in Diabatic Annular Two-Phase Flows," Journal of Power Technologies, vol. 94, pp. 85-95, 2014.
[10]
H. Anglart, "Modelling of Liquid Film Flow in Annuli," Journal of Power Technologies, vol. 94, pp. 8-15, 2014.
[11]
D. Caraghiaur, C. Adamsson and H. Anglart, "Deposition of Inertial Drops in Eulerian Formulation," in Proceedings of NURETH-15, 2013.
[12]
[14]
H. Anglart, Applied Reactor Technology. 1st ed. Warsaw, Poland : Warsaw University of Technology Publishing House, 2013.
[15]
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.
[17]
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.
[19]
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.
[20]
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.
[21]
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.
[23]
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.
[24]
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.
[25]
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.
[26]
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.
[27]
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.
[28]
R. Pegonen et al., "Hot fuel element thermal-hydraulics in the Jules Horowitz Reactor," Nuclear Engineering and Design, vol. 300, pp. 149-160, 2016.
[29]
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.
[30]
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.
[31]
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.
[32]
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.
[33]
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.
[34]
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.
[35]
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.
[36]
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.
[37]
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.
[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]
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.
[40]
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.
[42]
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.
[43]
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.
[44]
B. Olsen and J. Dufek, "Fission source sampling in coupled Monte Carlo simulations," Kerntechnik (1987), vol. 82, no. 2, pp. 206-209, 2017.
[45]
M. Bergagio, "Experimental analysis of thermal mixing at reactor conditions," Licentiate thesis : KTH Royal Institute of Technology, TRITA-FYS, 2016:74, 2016.
[46]
A. Riber Marklund et al., "Passive acoustic leak detection for sodium fast reactors using hidden Markov models," IEEE Transactions on Nuclear Science, 2016.
[47]
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.
[49]
S. A. Qvist et al., "Autonomous Reactivity Control (ARC) - Principles, geometry and design process," Nuclear Engineering and Design, vol. 307, pp. 249-274, 2016.
[50]
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.
Page responsible:Janne Wallenius
Belongs to: Nuclear Engineering
Last changed: Apr 19, 2018