Publikationer av Janne Wallenius
Refereegranskade
Artiklar
[1]
F. Dehlin och J. Wallenius, "Activation analysis of the lead coolant in SUNRISE-LFR," Nuclear Engineering and Design, vol. 414, 2023.
[2]
F. Dehlin, J. Wallenius och S. Bortot, "An analytic approach to the design of passively safe lead-cooled reactors (vol 169, 108971, 2022)," Annals of Nuclear Energy, vol. 181, 2023.
[3]
Z.-N. Huang et al., "Analysis of the stress field in the reactor vessel of the China Initiative Accelerator Driven System during postulated ULOF and UTOP transients," Annals of Nuclear Energy, vol. 194, 2023.
[4]
D. -. Wang et al., "Finite element analysis of the main reactor vessel in the China Initiative Accelerator Driven System," Engineering Failure Analysis, vol. 146, 2023.
[5]
C. Reale Hernandez, J. Wallenius och J. Luxat, "Simulation of a loss of flow transient of a small Lead-Cooled reactor using a CFD-Based model," Nuclear Engineering and Design, vol. 412, 2023.
[6]
Y. Mishchenko et al., "Thermophysical properties and oxidation behaviour of the U0.8Zr0.2N solid solution," Nuclear Materials and Energy, vol. 35, 2023.
[7]
G. Wang et al., "Transient analyses for China initiative Accelerator Driven System using the extended BELLA code," Annals of Nuclear Energy, vol. 190, 2023.
[8]
F. Dehlin, J. Wallenius och S. Bortot, "An analytic approach to the design of passively safe lead-cooled reactors," Annals of Nuclear Energy, vol. 169, s. 108971-108971, 2022.
[9]
J. Wallenius, "An improved correlation for gas release from nitride fuels," Journal of Nuclear Materials, vol. 558, 2022.
[10]
D. R. Costa et al., "Coated ZrN sphere-UO2 composites as surrogates for UN-UO2 accident tolerant fuels," Journal of Nuclear Materials, vol. 567, s. 153845, 2022.
[11]
C. R. Hernandez et al., "Development of a CFD-based model to simulate loss of flow transients in a small lead-cooled reactor," Nuclear Engineering and Design, vol. 392, s. 111773, 2022.
[12]
B. Xi et al., "Influence of TIG and Laser Welding Processes of Fe-10Cr-4Al-RE Alloy Cracks Overlayed on 316L Steel Plate," Materials, vol. 15, no. 10, s. 3541, 2022.
[13]
D. R. Costa et al., "Interface interactions in UN-X-UO2 systems (X = V, Nb, Ta, Cr, Mo, W) by pressure-assisted diffusion experiments at 1773 K," Journal of Nuclear Materials, vol. 561, s. 153554-153554, 2022.
[14]
Y. Mishchenko et al., "Potential accident tolerant fuel candidate : Investigation of physical properties of the ternary phase U2CrN3," Journal of Nuclear Materials, vol. 568, 2022.
[15]
D.-S. Wang et al., "Analysis of the Accelerator-Driven System Fuel Assembly during the Steam Generator Tube Rupture Accident," Materials, vol. 14, no. 8, 2021.
[16]
Y. Mishchenko et al., "Design and fabrication of UN composites : From first principles to pellet production," Journal of Nuclear Materials, vol. 553, s. 153047, 2021.
[17]
S. Yang et al., "Development of a welding process to overlay FeCrAl alloy on a thin wall austenitic stainless steel tube," Nuclear Materials and Energy, vol. 27, 2021.
[18]
D. R. Costa et al., "Oxidation of UN/U2N3-UO2 composites : an evaluation of UO(2 )as an oxidation barrier for the nitride phases," Journal of Nuclear Materials, vol. 544, 2021.
[19]
Y. Mishchenko et al., "Uranium nitride advanced fuel : an evaluation of the oxidation resistance of coated and doped grains," Journal of Nuclear Materials, vol. 556, 2021.
[20]
J. Wallenius, "Anomalous reactivity swing in the 238U-233U system," Annals of Nuclear Energy, vol. 139, 2020.
[21]
C. Reale Hernandez, J. Wallenius och J. Luxat, "Dynamic sensitivity and uncertainty analysis of a small lead cooled reactor," Annals of Nuclear Energy, vol. 144, 2020.
[22]
C. Ekberg et al., "Fuel fabrication and reprocessing issues : the ASGARD project," EPJ Nuclear Sciences & Technologies., vol. 6, 2020.
[23]
D. R. Costa et al., "UN microspheres embedded in UO2 matrix : An innovative accident tolerant fuel," Journal of Nuclear Materials, vol. 540, 2020.
[24]
J. Wallenius och S. Bortot, "A new paradigm for breeding of nuclear fuel," Annals of Nuclear Energy, vol. 133, s. 816-819, 2019.
[25]
J. Wallenius, "Maximum efficiency nuclear waste transmutation," Annals of Nuclear Energy, vol. 125, s. 74-79, 2019.
[26]
J. Wallenius och S. Bortot, "A small lead-cooled reactor with improved Am-burning and non-proliferation characteristics," Annals of Nuclear Energy, vol. 122, s. 193-200, 2018.
[27]
J. Wallenius et al., "Design of SEALER, a very small lead-cooled reactor for commercial power production in off-grid applications," Nuclear Engineering and Design, vol. 338, s. 23-33, 2018.
[28]
K. Johnson et al., "Oxidation of accident tolerant fuel candidates," Journal of Nuclear Science and Technology, vol. 54, no. 3, s. 280-286, 2017.
[29]
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, s. 325-345, 2017.
[30]
K. D. Johnson et al., "Fabrication and microstructural analysis of UN-U3Si2 composites for accident tolerant fuel applications," Journal of Nuclear Materials, vol. 477, s. 18-23, 2016.
[31]
K. D. Johnson et al., "Spark plasma sintering and porosity studies of uranium nitride," Journal of Nuclear Materials, vol. 473, s. 13-17, 2016.
[32]
S. Bortot, E. Suvdantsetseg och J. Wallenius, "BELLA : a multi-point dynamics code for safety-informed design of fast reactors," Annals of Nuclear Energy, vol. 85, s. 228-235, 2015.
[33]
P. R. Hania et al., "Irradiation and post-irradiation examination of uranium-free nitride fuel," Journal of Nuclear Materials, vol. 466, s. 597-605, 2015.
[34]
E. Suvdantsetseg och J. Wallenius, "An assessment of prompt neutron reproduction time in a reflector dominated fast critical system : ELECTRA," Annals of Nuclear Energy, vol. 71, s. 159-165, 2014.
[35]
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, s. 548-551, 2014.
[36]
Y. Zhang och J. Wallenius, "Upper limits to americium concentration in large sized sodium-cooled fast reactors loaded with metallic fuel," Annals of Nuclear Energy, vol. 70, s. 180-187, 2014.
[37]
J. Zakova och J. Wallenius, "Multirecycling of Pu, Am and Cm in BWR," Annals of Nuclear Energy, vol. 58, s. 255-267, 2013.
[38]
E. Suvdantsetseg, J. Wallenius och S. Bortot, "Optimization of the reactivity control drum system of ELECTRA (vol 252C, pg 209, 2012)," Nuclear Engineering and Design, vol. 255, s. 376-376, 2013.
[39]
Y. Zhang, J. Wallenius och M. Jolkkonen, "Transmutation of americium in a large sized sodium-cooled fast reactor loaded with nitride fuel," Annals of Nuclear Energy, vol. 53, s. 26-34, 2013.
[40]
J. Wallenius, E. Suvdantsetseg och A. Fokau, "Electra : European Lead-Cooled Training Reactor," Nuclear Technology, vol. 177, no. 3, s. 303-313, 2012.
[41]
J. Zakova och J. Wallenius, "Fuel residence time in BWRs with nitride fuels," Annals of Nuclear Energy, vol. 47, s. 182-191, 2012.
[42]
E. Suvdantsetseg, J. Wallenius och S. Bortot, "Optimization of the reactivity control drum system of ELECTRA," Nuclear Engineering and Design, vol. 252, no. 1, s. 209-214, 2012.
[43]
J. Wallenius, "Physics of Americium transmutation," Nuclear Engineering and Technology, vol. 44, no. 2, s. 199-206, 2012.
[44]
M. Tesinsky, Y. Zhang och J. Wallenius, "The impact of americium on the ULOF and UTOP transients of the European Lead-cooled SYstem (ELSY)," Annals of Nuclear Energy, vol. 47, s. 104-109, 2012.
[45]
M. Tesinsky et al., "The impact of americium on transients in the European Lead-cooled SYstem ELSY loaded with nitride fuel," Annals of Nuclear Energy, vol. 50, s. 56-62, 2012.
[46]
J. Wallenius, N. Sandberg och K. Henriksson, "Atomistic modelling of the Fe-Cr-C system," Journal of Nuclear Materials, vol. 415, no. 3, s. 316-319, 2011.
[47]
Y. Zhang et al., "Physics and safety studies of a compact ADS design loaded with nitride fuel," Annals of Nuclear Energy, vol. 38, no. 11, s. 2350-2355, 2011.
[48]
J. Zakova och J. Wallenius, "Void reactivity feedback in BWRs with MA bearing MOX fuels," Annals of Nuclear Energy, vol. 38, no. 9, s. 1968-1977, 2011.
[49]
A. Fokau et al., "A source efficient ADS for minor actinides burning," Annals of Nuclear Energy, vol. 37, no. 4, s. 540-545, 2010.
[50]
Y. Zhang, J. Wallenius och A. Fokau, "Transmutation of americium in a medium size sodium cooled fast reactor design," Annals of Nuclear Energy, vol. 37, no. 5, s. 629-638, 2010.
[51]
M. Pukari et al., "Vacancy formation and solid solubility in the U-Zr-N system," Journal of Nuclear Materials, vol. 406, no. 3, s. 351-355, 2010.
[52]
S. L. Dudarev et al., "The EU programme for modelling radiation effects in fusion reactor materials : An overview of recent advances and future goals," Journal of Nuclear Materials, vol. 386, s. 1-7, 2009.
[53]
W. Maschek et al., "Accelerator driven systems for transmutation : Fuel development, design and safety," Progress in nuclear energy (New series), vol. 50, no. 2-6, s. 333-340, 2008.
[54]
K. O. E. Henriksson, N. Sandberg och J. Wallenius, "Carbides in stainless steels : Results from ab initio investigations," Applied Physics Letters, vol. 93, no. 19, 2008.
[55]
N. Sandberg, K. O. E. Henriksson och J. Wallenius, "Carbon impurity dissolution and migration in bcc Fe-Cr : First-principles calculations," Physical Review B. Condensed Matter and Materials Physics, vol. 78, no. 9, 2008.
[56]
J. Wallenius och D. Westlén, "Hafnium clad fuels for fast spectrum BWRs," Annals of Nuclear Energy, vol. 35, no. 1, s. 60-67, 2008.
[57]
L. Malerba, A. Caro och J. Wallenius, "Multiscale modelling of radiation damage and phase transformations : The challenge of FeCr alloys," Journal of Nuclear Materials, vol. 382, no. 2-3, s. 112-125, 2008.
[58]
P. Olsson, C. Domain och J. Wallenius, "Ab initio study of Cr interactions with point defects in bcc Fe," Physical Review B. Condensed Matter and Materials Physics, vol. 75, no. 1, s. 014110, 2007.
[59]
V. Pontikis, V. Russier och J. Wallenius, "An analytic n-body potential for bcc iron," Nuclear Instruments and Methods in Physics Research Section B : Beam Interactions with Materials and Atoms, vol. 255, no. 1, s. 37-40, 2007.
[60]
L. Malerba et al., "Modelling of radiation damage in Fe-Cr alloys," Journal of ASTM International, vol. 4, no. 6, 2007.
[61]
J. Wallenius et al., "Simulation of thermal ageing and radiation damage in Fe-Cr," Nuclear Instruments and Methods in Physics Research Section B : Beam Interactions with Materials and Atoms, vol. 255, no. 1, s. 68-74, 2007.
[62]
N. Juslin et al., "Simulation of threshold displacement energies in FeCr," Nuclear Instruments and Methods in Physics Research Section B : Beam Interactions with Materials and Atoms, vol. 255, no. 1, s. 75-77, 2007.
[63]
K. Tucek et al., "Studies of an accelerator-driven transuranium burner with hafnium-based inert matrix fuel," Nuclear Technology, vol. 157, no. 3, s. 277-298, 2007.
[64]
D. A. Terentyev et al., "Displacement cascades in Fe-Cr : A molecular dynamics study," Journal of Nuclear Materials, vol. 349, no. 1-2, s. 119-132, 2006.
[65]
D. Terentyev et al., "Effect of the interatomic potential on the features of displacement cascades in alpha-Fe : A molecular dynamics study," Journal of Nuclear Materials, vol. 351, no. 03-jan, s. 65-77, 2006.
[66]
P. Olsson, I. A. Abrikosov och J. Wallenius, "Electronic origin of the anomalous stability of Fe-rich bcc Fe-Cr alloys," Physical Review B. Condensed Matter and Materials Physics, vol. 73, no. 10, s. 104416, 2006.
[67]
J. Wallenius, S. Pillon och L. Zaboudko, "Fuels for accelerator-driven systems," Nuclear Instruments and Methods in Physics Research Section A : Accelerators, Spectrometers, Detectors and Associated Equipment, vol. 562, no. 2, s. 625-629, 2006.
[68]
K. Nordlund, J. Wallenius och L. Malerba, "Molecular dynamics simulations of threshold displacement energies in Fe," Nuclear Instruments and Methods in Physics Research Section B : Beam Interactions with Materials and Atoms, vol. 246, no. 2, s. 322-332, 2006.
[69]
D. Westlén och J. Wallenius, "On TiN-particle fuel based helium-cooled transmutation systems," Annals of Nuclear Energy, vol. 33, no. 16, s. 1322-1328, 2006.
[70]
S. Pillon och J. Wallenius, "Oxide and nitride TRU fuels : Lessons drawn from the CONFIRM and FUTURE projects of the 5th European Framework Program," Nuclear science and engineering, vol. 153, no. 3, s. 245-252, 2006.
[71]
P. Seltborg och J. Wallenius, "Proton source efficiency for heterogeneous distribution of actinides in the core of an accelerator-driven system," Nuclear science and engineering, vol. 154, no. 2, s. 202-214, 2006.
[72]
M. Eriksson et al., "Inherent Safety of Fuels for Accelerator-driven Systems," Nuclear Technology, vol. 151, no. 3, s. 314-333, 2005.
[73]
D. Westlén och J. Wallenius, "Neutronic and Safety Aspects of a Gas-Cooled Subcritical Core for Minor Actinide Transmutation," Nuclear Technology, vol. 154, no. 1, s. 41-51, 2005.
[74]
J. Wallenius och M. Eriksson, "Neutronics of minor-actinide burning accelerator-driven systems with ceramic fuel," Nuclear Technology, vol. 152, no. 3, s. 367-381, 2005.
[75]
P. Olsson et al., "Two-band modeling of alpha-prime phase formation in Fe-Cr," Physical Review B. Condensed Matter and Materials Physics, vol. 72, no. 21, s. 1-6, 2005.
[76]
K. Tucek, J. Wallenius och W. Gudowski, "Coolant void worth in fast breeder reactors and accelerator-driven transuranium and minor-actinide burners," Annals of Nuclear Energy, vol. 31, no. 15, s. 1783-1801, 2004.
[77]
J. Wallenius et al., "Development of an EAM potential for simulation of radiation damage in Fe-Cr alloys," Journal of Nuclear Materials, vol. 329-33, s. 1175-1179, 2004.
[78]
J. Wallenius et al., "Modeling of chromium precipitation in Fe-Cr alloys," Physical Review B Condensed Matter, vol. 69, s. 094103, 2004.
[79]
L. Malerba et al., "Molecular dynamics simulation of displacement cascades in Fe-Cr alloys," Journal of Nuclear Materials, vol. 329-33, s. 1156-1160, 2004.
[80]
M. Jolkkonen, M. Streit och J. Wallenius, "Thermo-chemical modelling of uranium-free nitride fuels," Journal of Nuclear Science and Technology, vol. 41, no. 4, s. 457-465, 2004.
[81]
P. Olsson et al., "Ab initio formation energies of Fe-Cr alloys," Journal of Nuclear Materials, vol. 321, no. 1, s. 84-90, 2003.
[82]
E. Lindroth, J. Wallenius och S. Jonsell, "Decay rates of excited muonic molecular ions," Physical Review A. Atomic, Molecular, and Optical Physics, vol. 68, no. 3, 2003.
[83]
P. Seltborg et al., "Definition and application of proton source efficiency in accelerator driven systems," Nuclear science and engineering, vol. 145, no. 3, s. 390-399, 2003.
[84]
J. Wallenius, "Neutronic aspects of inert matrix fuels for application in ADS," Journal of Nuclear Materials, vol. 320, no. 02-jan, s. 142-146, 2003.
[85]
J. Wallenius et al., "Application of burnable absorbers in an accelerator-driven system," Nuclear science and engineering, vol. 137, no. 1, s. 96-106, 2001.
[86]
J. Wallenius et al., "Muonic atom deexcitation via formation of metastable molecular states in light of experimental verification," Hyperfine Interactions, vol. 138, no. 04-jan, s. 285-288, 2001.
[87]
W. Gudowski et al., "Review of the European project - Impact of Accelerator-Based Technologies on Nuclear Fission Safety (IABAT)," Progress in nuclear energy (New series), vol. 38, no. 1-2, s. 135-151, 2001.
Konferensbidrag
[88]
I. Morelová et al., "IAEA'S Coordinated Research Projects on Thermal Hydraulics of Fast Reactors," i Proceedings of the 30th International Conference on Nuclear Engineering "Nuclear, Thermal, and Renewables: United to Provide Carbon Neutral Power", ICONE 2023, 2023.
[89]
D. R. Costa et al., "Coated UN microspheres embedded in UO2 matrix as an innovative advanced technology fuel: Early progress," i TopFuel 2021 Light Water Reactor Fuel Performance Conference, Santander, Spain, October 24-28, 2021., 2021.
[90]
J. Wallenius, S. Bortot och I. Mickus, "Unprotected transients in sealer : A small lead-cooled reactor for commercial power production in Arctic Regions," i International Conference on Physics of Reactors, PHYSOR 2018 : Reactor Physics Paving the Way Towards More Efficient Systems, 2018, s. 1437-1448.
[91]
J. Wallenius och M. Hussein, "Uranium nitride fuels for application in CANDU reactors," i International Conference on Physics of Reactors, PHYSOR 2018 : Reactor Physics Paving the Way Towards More Efficient Systems, 2018, s. 3603-3611.
[92]
K. Lambrinou et al., "Corrosion-resistant ternary carbides for use in heavy liquid metal coolants," i Ceramic Engineering and Science Proceedings, 2016, s. 19-34.
[93]
F. Delage et al., "ADS fuel developments in Europe : Results from the EUROTRANS integrated project," i Energy Procedia, 2011, s. 303-313.
[94]
G. J. Ackland, D. J. Hepburn och J. Wallenius, "Interatomic forces for transition metals including magnetism," i 139th Annual Meeting & Exhibition - Supplemental Proceedings, Vol 2 : Materials Characterization, Computation And Modeling And Energy, 2010, s. 85-92.
Icke refereegranskade
Böcker
[95]
Kapitel i böcker
[96]
[97]
J. Wallenius, "Nitride Fuels," i Comprehensive Nuclear Materials: Second Edition, : Elsevier BV, 2020, s. 88-101.
Patent
Patent
[98]
M. Jolkkonen, K. Johnson och J. Wallenius, "Fuel for water-cooled nuclear reactors," WIPO (PCT) WO2016122374A1, 2016.
[99]
J. Wallenius, M. Jolkkonen och M. Radwan, "Nitride nuclear fuel and method for its production," , 2010.
Senaste synkning med DiVA:
2024-05-12 03:06:12