Research Areas: Advanced Characterization; Nuclear; Materials Characterization; Materials Properties and Performance
Biography: Daniel Jadernas is an R&D Scientist at Idaho National Laboratory’s Materials and Fuel Complex. Working at the Irradiated Materials Characterization Laboratory, Daniel is the focused ion beam (FIB) Instrument Group Leader. He is responsible for research activities that utilize FIBs and the development of novel techniques for characterizing materials. Daniel has 13 years of experience using electron and ion optical techniques in conjunction with related analytical techniques (EDS, WDS, EBSD, EELS, etc.) in both academic and industrial settings with a focus on nuclear materials. Daniel graduated with a Master of Science in Physics from the University of Linkoping, Sweden. After that, he spent three years performing academic research at University of Linkoping before transitioning to Studsvik Nuclear AB where he worked for eight years in both managerial and specialist roles with post-irradiation examinations of commercial reactor fuel and fuel components. Daniel has authored more than forty scientific papers and given three invited presentations related to nuclear materials research.
Master of Science in Physics, University of Linkoping, Sweden, 2006
Member of the American Nuclear Society Ad-hoc journal reviewer Grant proposal reviewer
T. Seymour, P. Frankel, L. Balogh, T. Ungár, S.P. Thompson, D. Jädernäs, J. Romero, L. Hallstadius, M.R. Daymond, G. Ribárik, M. Preuss. "Evolution of dislocation structure in neutron irradiated Zircaloy-2 studied by synchrotron x-ray line profile analysis", Acta Materialia, Volume 126, 2017.
Harte, D. Jädernäs, M. Topping, P. Frankel, C.P. Race, J. Romero, L. Hallstadius, E.C. Darby, M. Preuss, "The effect of matrix chemistry on dislocation evolution in an irradiated Zr alloy", Acta Materialia, Volume 130, 2017.
Harte, M. Topping, P. Frankel, D. Jädernäs, J. Romero, L. Hallstadius, E.C. Darby, M. Preuss, "Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy", Journal of Nuclear Materials, Volume 487, 2017.
J. Chen, D. Jädernäs, F. Lindberg, M. Bjurman, K. Kese, A. Jenssen, M. Cocco, H. Johansson, "Microstructures of oxide films formed in Alloy 182 BWR core shroud support leg cracks", Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
Jenssen, J. Chen, F. Lindberg, D. Jadernas, P. Ekstrom, P. Efsing. "Effect of Neutron Irradiation on the Oxides formed on Type 316 Stainless Steel", Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
M. Bjurman, D. Jädernäs, K. Kese, A. Jenssen, J. Chen, M. Cocco, H. Johansson. "Root cause analysis of cracking in Alloy 182 BWR core shroud support leg cracks", Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
D. Jädernäs, F. Corleoni, P. Tejland, A. Puranen, J. Matsunaga, "Chemical and Structural Characterization of Ramp Tested Fuel with Different Additives", OECD/NEA/WGFS Workshop on Pellet Cladding Interaction
M. Topping, A. Harte, P. Frankel, C. Race, G. Sundell, M. Thuvander, H.-O. Andrén, D. Jadernas, P. Teiland, J. Romero, E. C. Darby, S. Dumbill, L. Hallstadius, M. Preuss. "The Effect of Iron on Dislocation Evolution in Model and Commercial Zirconium Alloys", 18th International Symposium on Zirconium in the Nuclear Industry, 2016
J. Karlsson, G. Grandi, C. Struzik, I. Porter, D. Schrire, E. Dalborg, A. Moeckel, D. Jädernäs, P. Magnusson, F. Corleoni, A. Puranen, "Fuel Performance Modeling of the Halden-Studsvik Counter-Part Test Rod", The Extended Halden Program Group Meeting 2016
P. Magnusson, C. Adamsson, D. Jädernäs, G. Rönnberg, D. Schrire, A. Alvestav, M. Seidl. "A study of transient FGR by integral LOCA tests", Light Water Reactor (LWR) Fuel Performance Meeting/Top Fuel 2016
J. Chen, D. Jadernas, M. Bjurman, F. Lindberg, K. Kese, A. Jenssen, H. Johansson, M. Cocco, "TEM Examination of Oxide Films Formed in the Crack Opening of Alloy 182 Weld Metal under BWR Normal Water Chemistry Conditions", Proceedings of the 20th Nuclear Plant Chemistry Conference, NPC 2016
EBSD in nuclear applications
D. Jädernäs, INVITED SPEAKER - 14th European Workshop on Modern Developments and Applications in Microbeam Analysis 2015.
O. Roth, A. Puranen, M. Granfors, D. Cui, C. Askeljung, D. Jädernäs, Overview of spent nuclear fuel properties affecting the release of radionuclides under long-term storage conditions, Miller Conference on Radiation Chemistry 2015
D. Jädernäs, P. Tejland, A. Puranen, M. Granfors, J. Matsunaga, PCI mitigation using fuel additives, Light Water Reactor (LWR) Fuel Performance Meeting/Top Fuel 2015.
Curti, A. Puranen, D. Grolimund, D. Jädernas, D. Sheptyakova, A. Mesbah, Characterization of selenium in UO2 spent nuclear fuel by micro X-ray absorption spectroscopy and its thermodynamic stability
Environmental Science: Processes & Impacts, 2015, 17, 1760-1768
Harte, T. Seymour, E.M. Francis, P. Frankel, S.P. Thompson, D. Jädernäs, J. Romero, L. Hallstadius and M. Preuss, Advances in Synchrotron X-Ray Diffraction and Transmission Electron Microscopy Techniques for the Investigation of Microstructure Evolution in Proton- and Neutron-Irradiated Zirconium Alloys
Journal of Materials Research - Volume 30, Issue 9 (Focus Issue: Characterization and Modeling of Radiation Damage on Materials: State of the Art, Challenges, and Protocols) May 2015, pp. 1349-1365.
D. Jädernäs, P. Tejland, Electron Backscatter Diffraction of Nuclear Materials - INVITED SPEAKER - Microscopy & Microanalysis 2014, Microsc. Microanal. 20 (Suppl 3), 2014.
Iron redistribution in a zirconium alloy after neutron and proton irradiation studied by energy-dispersive E.M. Francis, A. Harte, P. Frankel, S.J. Haigh, D. Jädernäs, J. Romero, L. Hallstadius, M. Preuss, X-ray spectroscopy (EDX) using an aberration corrected (scanning) transmission electron microscope (Corrigendum in Volume 467, Part 1, December 2015, Pages 395–396). Journal of Nuclear Materials, Volume 454, Issues 1–3, November 2014, pp. 387–397.
E. Curti, A. Froideval, M. Martin, A. Bullemar, I. Gunther-Leopold, D. Jädernäs, A. Puranen, O. Roth, D. Grolimund, C.N. Borca, A. Valea, X-Ray Absorption Spectroscopy of Selenium in Unirradiated UO2 and High-Burnup UO2 Spent Fuel From the Leibstadt and Oskarshamn-3 Reactors, Final Workshop Proceedings of the Collaborative Project "Fast / Instant Release of Safety Relevant Radionuclides from Spent Nuclear Fuel".
P. Magnusson, A. Puranen, D. LeBouch, D. Jädernäs, G. Lysell, An experimental and finite element modeling study of cladding strain and localized stresses under simulated iodine-induced stress corrosion cracking PCI, LWR Fuel Performance Meeting/TopFuel 2014.
D. Jädernäs, F. Corleoni, A. Puranen, M. Gransfors, G. Lysell, P. Tejland, D. Lutz, L. Hallstadius, Microstructural and Chemical Characterization of Ramp Tested Additive Fuels, LWR Fuel Performance Meeting/TopFuel 2013.
Puranen, M. Granfors, P. Askeljung, D. Jädernäs, M. Flanagan, Burnup Effects on Fine Fuel G. Pan, A. Garde, R. Källström, A. Atwood, D. Jädernäs. Fragmentation in Simulated LOCA Testing, LWR Fuel Performance Meeting/TopFuel 2013.
High Burnup OPTIMIZED ZIRLO(TM) Cladding Performance, LWR Fuel Performance Meeting/TopFuel 2013.
J. Romero, M. Dahlbäck, M. Ivermark, L. Hallstadius, D. Jadernas, G. Ledergerber, Understanding the drivers of in-reactor growth of beta-quenched Zircaloy 2 BWR channels, 17th International Symposium on Zirconium in the Nuclear Industry 2013.
Awarded best master thesis by the Surface Science Society
Light Water Reactor Fuel Expert role and group lead for the Focused Ion Beam (FIB) group. Principal investigator for development and post irradiation research and development projects. Research activities that use FIBs and the development of novel techniques for characterizing materials.