"International round robin on ion irradiation of alloy T91 and comparison with neutron irradiation" C. Cabet, C. Kaden, M.H. Mayoral, C. Pareige, D. Bhattacharyya, C. David, C. Hardie, D. Terentyev, W. Weber, T. Wei, F. Naab, V. Pauly, I. Swainson, M.S. Veshchunov, G.S. Was, [2025] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2025.156065 | |
"Microstructural study of the thermal stability of a thermomechanically treated T91 steel by TEM in situ annealing" Mercedes Hernández-Mayoral, Rebeca Hernández, Marta Serrano, Elvira Oñorbe, [2022] Nuclear Materials and Energy · DOI: 10.1016/j.nme.2022.101213 · ISSN: 2352-1791 | |
"Investigation of coarsening of oxide nanoparticles at 1400 K and its effect on the microstructure formation of an ODS Eurofer steel" T.P. Davis, M.H. Mayoral, A. Kumar, H. Schut, J. Sietsma, V.S.M. Pereira, [2022] Materials Characterization · DOI: 10.1016/j.matchar.2022.111723 · ISSN: 1044-5803 | |
"Effect of Neutron Flux on an Irradiation-Induced Microstructure and Hardening of Reactor Pressure Vessel Steels"
Mercedes Hernández-Mayoral, Elvira Oñorbe, Auriane Etienne, Bertrand Radiguet, Eric Hirschmann, Andreas Wagner, Hieronymus Hein, Frank Bergner, Andreas Ulbricht,
[2022]
Metals
· DOI: 10.3390/met12030369
The existing knowledge about the effect of neutron irradiation on the mechanical properties of reactor pressure vessel steels under reactor service conditions relies to a large extent on accelerated irradiations realized by exposing steel samples to a higher neutron flux. A deep understanding of flux effects is, therefore, vital for gaining service-relevant insight into the mechanical property degradation. The existing studies on flux effects often suffer from incomplete descriptions of the irradiation-induced microstructure. Our study aims to give a detailed picture of irradiation-induced nanofeatures by applying complementary methods using atom probe tomography, positron annihilation, small-angle neutron scattering and transmission electron microscopy. The characteristics of the irradiation-induced nanofeatures and the dominant factors responsible for the observed increase of Vickers hardness are identified. Microstructural changes due to high flux conditions are smaller nm-sized solute atom clusters with almost the same volume fraction and a higher concentration of vacancies and sub-nm vacancy clusters compared to low flux conditions. The results rationalize why pronounced flux effects on the nanofeatures, in particular on solute atom clusters, only give rise to small or moderate flux effects on hardening. |
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"Creep Properties of 9Cr and 14Cr ODS Tubes Tested by Inner Gas Pressure" U. Ehrnstén, N. Mozzani, J. Rantala, M. Walter, A. Hobt, J. Aktaa, E. Oñorbe, M. Hernandez-Mayoral, A. Ulbricht, S. Gicquel, L. Frank, Y. de Carlan, D. Sornin, [2021] Metallurgical and Materials Transactions A · DOI: 10.1007/s11661-021-06327-0 | |
"Multiscale modelling for fusion and fission materials: the M4F project" M.J. Caturla, E. Gaganidze, C. Kaden, M.J. Konstantinović, P. Olsson, C. Robertson, D. Rodney, A.M. Ruiz-Moreno, M. Serrano, J. Aktaa, N. Anento, S. Austin, A. Bakaev, J.P. Balbuena, F. Bergner, F. Boioli, M. Boleininger, G. Bonny, N. Castin, J.B.J. Chapman, P. Chekhonin, M. Clozel, B. Devincre, L. Dupuy, G. Diego, S.L. Dudarev, C.-C. Fu, R. Gatti, L. Gélébart, B. Gómez-Ferrer, D. Gonçalves, C. Guerrero, P.M. Gueye, P. Hähner, S.P. Hannula, Q. Hayat, M. Hernández-Mayoral, J. Jagielski, N. Jennett, F. Jiménez, G. Kapoor, A. Kraych, T. Khvan, L. Kurpaska, A. Kuronen, N. Kvashin, O. Libera, P.-W. Ma, T. Manninen, M.-C. Marinica, S. Merino, E. Meslin, F. Mompiou, F. Mota, H. Namburi, C.J. Ortiz, C. Pareige, M. Prester, R.R. Rajakrishnan, M. Sauzay, A. Serra, I. Simonovski, F. Soisson, P. Spätig, D. Tanguy, D. Terentyev, M. Trebala, M. Trochet, A. Ulbricht, M.Vallet, K. Vogel, T. Yalcinkaya, J. Zhao, L. Malerba, [2021] Nuclear Materials and Energy · DOI: 10.1016/j.nme.2021.101051 · ISSN: 2352-1791 | |
"A NEA review on innovative structural materials solutions, including advanced manufacturing processes for nuclear applications based on technology readiness assessment" C. Cabet, S. Cornet, Y. Dai, J. Gan, M. Hernández Mayoral, R. Hernández, A. Jianu, L. Malerba, S.A. Maloy, J. Marrow, S. Ohtsuka, N. Okubo, M.A. Pouchon, A. Puype, E. Stergar, M. Serrano, D. Terentyev, Y.G. Wang, A. Weisenburger, F. Balbaud, [2021] Nuclear Materials and Energy · DOI: 10.1016/j.nme.2021.101006 · EID: 2-s2.0-85104934701 · ISSN: 2352-1791 | |
"Depth distribution of irradiation-induced dislocation loops in an Fe-9Cr model alloy irradiated with Fe ions: The effect of ion energy" P. Chekhonin, C. Kaden, M. Hernández-Mayoral, S. Akhmadaliev, F. Bergner, K. Vogel, [2021] Nuclear Materials and Energy · DOI: 10.1016/j.nme.2021.101007 · EID: 2-s2.0-85104915179 · ISSN: 2352-1791 | |
"TEM Observation of Loops Decorating Dislocations and Resulting Source Hardening of Neutron-Irradiated Fe-Cr Alloys"
Mercedes Hernández-Mayoral, Cornelia Heintze, Milan J. Konstantinović, Lorenzo Malerba, Cristelle Pareige, Frank Bergner,
[2020]
Metals
· DOI: 10.3390/met10010147
Several open issues remain concerning the quantitative understanding of irradiation hardening in high-Cr steels. One of these issues is addressed here by correlating yield points that are observed in stress-strain curves with dislocation decoration observed by TEM for neutron-irradiated Fe-Cr alloys. It is found that both higher neutron exposure and higher Cr content promote irradiation-induced loops to arrange preferentially along dislocation lines. Consequently, the activation of dislocation sources requires unlocking from the decorating loops, thus resulting in a yield drop. This process is considered within the source hardening model as opposed to the dispersed barrier hardening model, the latter aimed to describe dislocation slip through a random array of obstacles. Microstructure-informed estimates of the unlocking stress are compared with measured values of the upper yield stress. As functions of neutron exposure, a cross-over from the dominance of dispersed-barrier hardening accompanied by smooth elastic-plastic transitions to the dominance of source hardening accompanied by yield drops is observed for Fe-9% Cr and Fe-12% Cr. |
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"Insights from atomistic models on loop nucleation and growth in α-Fe thin films under Fe+ 100 keV irradiation" M.J. Aliaga, I. Dopico, M. Hernández-Mayoral, L. Malerba, I. Martin-Bragado, M.J. Caturla, J.P. Balbuena, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.04.030 | |
"Insights from atomistic models on loop nucleation and growth in α-Fe thin films under Fe+ 100 keV irradiation" M.J. Aliaga, I. Dopico, M. Hernández-Mayoral, L. Malerba, I. Martin-Bragado, M.J. Caturla, J.P. Balbuena, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.04.030 · EID: 2-s2.0-85065120058 | |
"Quantification of APT physical limitations on chemical composition of precipitates in Fe–Cr alloys" Bertrand Radiguet, Gerald Da Costa, Philippe Pareige, Manuel Roussel, Mercedes Hernandez-Mayoral, Cristelle Pareige, Constantinos Hatzoglou, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.05.022 | |
"Study of the microstructure and small punch behavior of a 9Cr ODS tube" Mercedes Hernández-Mayoral, Alasdair Morrison, Marta Serrano, Elvira Oñorbe, [2019] Nuclear Materials and Energy · DOI: 10.1016/j.nme.2019.100698 · ISSN: 2352-1791 | |
"Effect of the heating rate on the microstructure of a ferritic ODS steel with four oxide formers (Y-Ti-Al-Zr) consolidated by spark plasma sintering (SPS)" A. García-Junceda, M. Serrano, M. Hernández-Mayoral, L.A. Diaz, M. Campos, E. Macía, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.02.043 | |
"Evolution of plastic deformation in heavily deformed and recrystallized tungsten of ITER specification studied by TEM" D. Terentyev, A. Bakaeva, K. Verbeken, M. Wirtz, M. Hernández-Mayoral, A. Dubinko, [2017] International Journal of Refractory Metals and Hard Materials · DOI: 10.1016/j.ijrmhm.2017.03.004 · EID: 2-s2.0-85015385728 | |
"Microstructure characterization and strengthening mechanisms of oxide dispersion strengthened (ODS) Fe-9%Cr and Fe-14%Cr extruded bars" F. Bergner, A. Etienne, J. Aktaa, Y. de Carlan, C. Heintze, D. Litvinov, M. Hernandez-Mayoral, E. Oñorbe, B. Radiguet, A. Ulbricht, A. Chauhan, [2017] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2017.07.060 · EID: 2-s2.0-85026747917 | |
"Sub-surface microstructure of single and polycrystalline tungsten after high flux plasma exposure studied by TEM" D. Terentyev, A. Bakaeva, M. Hernández-Mayoral, G. De Temmerman, L. Buzi, J.-M. Noterdaeme, B. Unterberg, A. Dubinko, [2017] Applied Surface Science · DOI: 10.1016/j.apsusc.2016.09.071 · EID: 2-s2.0-84992468393 | |
"Transmission electron microscopy investigation of the microstructure of Fe-Cr alloys induced by neutron and ion irradiation at 300°C" C. Heintze, E. Oñorbe, M. Hernández-Mayoral, [2016] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2016.03.002 · EID: 2-s2.0-84961572856 | |
"Irradiation hardening of Fe-9Cr-based alloys and ODS Eurofer: Effect of helium implantation and iron-ion irradiation at 300 °c including sequence effects" F. Bergner, M. Hernández-Mayoral, R. Kögler, G. Müller, A. Ulbricht, C. Heintze, [2016] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2015.12.041 · EID: 2-s2.0-84953294708 | |
"Effect of neutron flux on the characteristics of irradiation-induced nanofeatures and hardening in pressure vessel steels" F. Bergner, R. Chaouadi, H. Hein, M. Hernández-Mayoral, M. Serrano, A. Ulbricht, E. Altstadt, A. Wagner, [2016] Acta Materialia · DOI: 10.1016/j.actamat.2015.11.027 · EID: 2-s2.0-84949649369 | |
"Microstructural modifications in tungsten induced by high flux plasma exposure: TEM examination" A Bakaeva, M Hernández-Mayoral, D Terentyev, G De Temmerman, J-M Noterdaeme, A Dubinko, [2016] Physica Scripta · DOI: 10.1088/0031-8949/t167/1/014030 · EID: 2-s2.0-84959926074 | |
"Application of a three-feature dispersed-barrier hardening model to neutron-irradiated Fe-Cr model alloys" C. Pareige, M. Hernández-Mayoral, L. Malerba, C. Heintze, F. Bergner, [2014] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2014.01.024 · EID: 2-s2.0-84894276791 | |
"Microstructural and mechanical characterisation of ODS ferritic alloys produced by mechanical alloying and spark plasma sintering"
M. Serrano, E. Oñorbe, A. García-Junceda, I. Hilger, B. Kloeden, T. Weissgaerber, A. Ulbricht, F. Bergner, B. Radiguet, A. Etienne, A. Shariq, C. D. Dewhurst, M. Hernández-Mayoral,
[2014]
Materials Science and Technology (United Kingdom)
· DOI: 10.1179/1743284714y.0000000555
· EID: 2-s2.0-84907687052
Powders with nominal composition Fe–14Cr–2W–0·4Ti were mechanically alloyed (MA) with Y2O3 in a planetary ball mill at two different rotational speeds. Consolidation of the as milled powders was performed by spark plasma sintering (SPS). As milled powders showed a highly deformed microstructure with elongated nanometre grains and, depending upon the rotational speed, different stages of the nanocluster evolution were observed to be produced. In the case of consolidated materials, grain growth occurred during the SPS process and it was possible to observe the influence of the MA parameters, with larger and more homogeneously distributed grains at the higher rotational speed. Additionally, Ti was observed to be incorporated to the nanoclusters after SPS, indicating a further step in their evolution during consolidation. The mechanical behaviour of the SPS compacts was evaluated by tensile and small punch testing also showing the influence of the MA parameters in the material behaviour. |
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"On anisotropy of ferritic ODS alloys"
A. García-Junceda, R. Hernández, M. H. Mayoral, M. Serrano,
[2014]
Energy Materials: Materials Science and Engineering for Energy Systems
· DOI: 10.1179/1743284714y.0000000552
· EID: 2-s2.0-84940526546
Ferritic oxide dispersion strengthened (ODS) alloys are candidate materials to be used as cladding for long term fast reactors, due to their high strength at high temperature and good swelling and irradiation resistances. The fabrication of cladding tubes is usually made by a succession of cold deformation steps where a deformation induced anisotropic microstructure could take place, which would affect the mechanical behaviour of the tube. The characterisation of this microstructural anisotropy is one of the key issues in the development of cladding ODS tubes. In this paper, the microstructural anisotropy of a Fe–14Cr–ODS extruded bar and a Fe–12Cr–ODS plate is characterised and its effect on the mechanical properties is analysed by tensile, impact and small punch testing. In both materials, a reduction of the ductility is observed in the transverse specimens. In addition, the fracture behaviour seems to be strongly dependent on the location of the crack plane regarding the elongated grained microstructure. |
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"Nanoscale characterization of ODS Fe-9%Cr model alloys compacted by spark plasma sintering" M. Hernández-Mayoral, A. Ulbricht, F. Bergner, A. Shariq, T. Weissgärber, H. Frielinghaus, C. Heintze, [2012] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2011.08.053 · EID: 2-s2.0-84863780028 | |
"Influence of the microstructure on the tensile and impact properties of a 14Cr ODS steel bar" M. Hernández-Mayoral, M. Serrano, A. García-Junceda, [2012] Materials Science and Engineering A · DOI: 10.1016/j.msea.2012.07.051 · EID: 2-s2.0-84865441340 | |
"Ion-irradiation-induced damage in Fe-Cr alloys characterized by nanoindentation" F. Bergner, M. Hernández-Mayoral, C. Heintze, [2011] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2010.12.196 · EID: 2-s2.0-80053595735 | |
"Microstructure of oxide dispersion strengthened Eurofer and iron-chromium alloys investigated by means of small-angle neutron scattering and transmission electron microscopy" F. Bergner, A. Ulbricht, M. Hernández-Mayoral, U. Keiderling, R. Lindau, T. Weissgärber, C. Heintze, [2011] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2010.11.102 · EID: 2-s2.0-80052935099 | |
"The temperature dependence of heavy-ion damage in iron: A microstructural transition at elevated temperatures" M.L. Jenkins, M. Hernández-Mayoral, M.A. Kirk, Z. Yao, [2010] Philosophical Magazine · DOI: 10.1080/14786430903430981 · EID: 2-s2.0-77958576290 | |
"Dynamic observations of heavy-ion damage in Fe and Fe-Cr alloys" Z. Yao, M. Hernández-Mayoral, M.A. Kirk, M.L. Jenkins, [2009] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2009.02.003 · EID: 2-s2.0-64649094980 | |
"Ion-irradiation-induced damage of steels characterized by means of nanoindentation" C. Recknagel, F. Bergner, M. Hernández-Mayoral, A. Kolitsch, C. Heintze, [2009] Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms · DOI: 10.1016/j.nimb.2009.01.122 · EID: 2-s2.0-65249115950 | |
"Small-angle neutron scattering study of neutron-irradiated iron and an iron-nickel alloy" A. Ulbricht, M. Hernandez-Mayoral, P.K. Pranzas, F. Bergner, [2008] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2007.07.008 · EID: 2-s2.0-38849161559 | |
"Heavy-ion irradiations of Fe and Fe-Cr model alloys Part 1: Damage evolution in thin-foils at lower doses" M. Hernández-Mayoral, M.L. Jenkins, M.A. Kirk, Z. Yao, [2008] Philosophical Magazine · DOI: 10.1080/14786430802380469 · EID: 2-s2.0-57049164872 | |
"Heavy-ion irradiations of Fe and Fe-Cr model alloys Part 2: Damage evolution in thin-foils at higher doses" Z. Yao, M.L. Jenkins, M.A. Kirk, M. Hernández-Mayoral, [2008] Philosophical Magazine · DOI: 10.1080/14786430802380477 · EID: 2-s2.0-57049122307 | |
"Kinetic Monte Carlo modelling of neutron irradiation damage in iron" E. Martínez, J.M. Perlado, P. Cepas, M.J. Caturla, M. Victoria, J. Marian, C. Arévalo, M. Hernández, D. Gómez, L. Gámez, [2007] Fusion Engineering and Design · DOI: 10.1016/j.fusengdes.2007.04.040 · EID: 2-s2.0-34948884554 | |
"Correlation between microstructure and mechanical properties of reduced activation modified F-82H ferritic martensitic steel" M. Hernández-Mayoral, J. Lapeña, A. M. Lancha, G. De Diego, P. Fernández, [2002] Materials Science and Technology · DOI: 10.1179/026708302225007411 · EID: 2-s2.0-0036862852 | |
"Growth mechanism of CBD-In(OH) |
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"Metallurgical properties of reduced activation martensitic steel Eurofer'97 in the as-received condition and after thermal ageing" A.M Lancha, J Lapeña, M Serrano, M Hernández-Mayoral, P Fernández, [2002] Journal of Nuclear Materials · DOI: 10.1016/s0022-3115(02)01013-9 · EID: 2-s2.0-0036943444 | |
"Direct comparison between modeling and experiment: An α-Fe ion implantation study" [2001] Materials Research Society Symposium - Proceedings · EID: 2-s2.0-0034877080 | |
"Metallurgical characterization of the reduced activation ferritic/martensitic steel Eurofer’97 on as-received condition" A.M Lancha, J Lapeña, M Hernández-Mayoral, P Fernández, [2001] Fusion Engineering and Design · DOI: 10.1016/s0920-3796(01)00563-4 · EID: 2-s2.0-0035518076 | |
"Interface segregation study by Auger electron spectroscopy of cold-worked AISI-304 and -304L stainless steels" M. Hern�ndez-Mayoral, A. M. Lancha, M. Garc�a-Mazar�o, [2000] Surface and Interface Analysis · DOI: 10.1002/1096-9918(200008)30:1<315::aid-sia802>3.0.co;2-k · EID: 2-s2.0-17544385054 | |
"Irradiation effect simulation in austenitic stainless steels by cold working and heat treatments,Simulación del efecto de la irradiación mediante el trabajado en frío y los tratamientos térmicos en dos aceros inoxidables austeníticos" [1998] Revista de Metalurgia (Madrid) · EID: 2-s2.0-0032153797 | |
"Effect of lead on Inconel 600 and Incoloy 800 oxide layers formed in simulated steam generator secondary environments" A.M. Lancha, M. Hernández, C. Maffiotte, M. García-Mazarío, [1996] Nuclear Engineering and Design · DOI: 10.1016/s0029-5493(97)85102-3 · EID: 2-s2.0-0042459857 | |
Source: ORCID/CrossRef using DOI |
The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Through peer-reviewed proposal processes, the NSUF provides researchers access to neutron, ion, and gamma irradiations, post-irradiation examination and beamline capabilities at Idaho National Laboratory and a diverse mix of university, national laboratory and industry partner institutions.
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