Nanoscale redistribution of alloying elements in high-burnup AXIOM-2 (X2®) and their effects on in-reactor corrosion
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Lingfeng He | F. Teng | M. Bachhav | A. Couet | Zefeng Yu
[1] M. Thuvander,et al. An atom probe tomography study of the chemistry of radiation-induced dislocation loops in Zircaloy-2 exposed to boiling water reactor operation , 2021, Journal of Nuclear Materials.
[2] K. Linton,et al. (S)TEM/EDS study of native precipitates and irradiation induced Nb-rich platelets in high-burnup M5® , 2021 .
[3] M. Preuss,et al. Characterisation of deuterium distributions in corroded zirconium alloys using high-resolution SIMS imaging , 2020 .
[4] Lingfeng He,et al. Effect of proton pre-irradiation on corrosion of Zr-0.5Nb model alloys with different Nb distributions , 2020 .
[5] C. Jang,et al. Short communication: “Effect of Nb on the electrical resistivity of ZrO2 layer formed on Zr alloys” , 2020 .
[6] B. Wirth,et al. The effect of local chemical environment on the energetics of stacking faults and vacancy platelets in α-zirconium , 2020 .
[7] Jian Luo,et al. A development mechanism of graded microstructures in iron-containing SiC fibers revealed by electron microscopy , 2020 .
[8] F. Faghihi,et al. Investigations of the fresh-core cycle-length and the average fuel depletion analysis of the NuScale core , 2020 .
[9] N. Gayathri,et al. Microstructural investigation of irradiation damage behavior of proton irradiated Zr-1 wt.% Nb fuel cladding alloy , 2020 .
[10] N. Kumar,et al. Biaxial Creep Behavior of Nb-Modified Zircaloys , 2019, Nuclear Technology.
[11] A. Voigt,et al. Deterministic 3D self-assembly of Si through a rim-less and topology-preserving dewetting regime , 2019 .
[12] P. Voyles,et al. Microstructure and microchemistry study of irradiation-induced precipitates in proton irradiated ZrNb alloys , 2019, Acta Materialia.
[13] Z. Cai,et al. Comprehensive investigation of the role of Nb on the oxidation kinetics of Zr-Nb alloys , 2019, Corrosion Science.
[14] M. Preuss,et al. Effect of Neutron and Ion Irradiation on the Metal Matrix and Oxide Corrosion Layer on Zr-1.0Nb Cladding Alloys , 2019, Acta Materialia.
[15] M. Bachhav,et al. Irradiation-induced Nb redistribution of ZrNb alloy: An APT study , 2019, Journal of Nuclear Materials.
[16] P. Burr,et al. First-principles calculations of solute transport in zirconium: Vacancy-mediated diffusion with metastable states and interstitial diffusion , 2019, Physical Review Materials.
[17] M. Preuss,et al. Effect of Nb and Fe on damage evolution in a Zr-alloy during proton and neutron irradiation , 2019, Acta Materialia.
[18] Gorakh M. Pawar,et al. Interpreting the Presence of an Additional Oxide Layer in Analysis of Metal Oxides–Metal Interfaces in Atom Probe Tomography , 2019, The Journal of Physical Chemistry C.
[19] F. Onimus,et al. Shape, orientation relationships and interface structure of beta-Nb nano-particles in neutron irradiated zirconium alloy , 2018, Journal of Nuclear Materials.
[20] D. Butt,et al. Detecting the Oxidation of Zircaloy Claddings by Infrared Interference , 2018 .
[21] P. Voorhees,et al. Nonequilibrium Solute Capture in Passivating Oxide Films. , 2018, Physical review letters.
[22] A. Wilkinson,et al. Understanding corrosion and hydrogen pickup of zirconium fuel cladding alloys: the role of oxide microstructure, porosity, suboxides, and second-phase particles , 2018 .
[23] M. Wenman,et al. The effect of Nb on the corrosion and hydrogen pick-up of Zr alloys , 2017 .
[24] M. Preuss,et al. The effect of matrix chemistry on dislocation evolution in an irradiated Zr alloy , 2017 .
[25] B. Ensor. THE NATURE OF UNSTABLE OXIDE GROWTH IN ZIRCONIUM AND ZIRCONIUM ALLOYS , 2016 .
[26] A. Heuer,et al. The Band Structure of Polycrystalline Al2O3 and Its Influence on Transport Phenomena , 2016 .
[27] P. Bagot,et al. Advances in atom probe tomography instrumentation: Implications for materials research , 2016, MRS Bulletin.
[28] Arthur T. Motta,et al. The coupled current charge compensation model for zirconium alloy fuel cladding oxidation: I. Parabolic oxidation of zirconium alloys , 2015 .
[29] M. Preuss,et al. The effect of Sn concentration on oxide texture and microstructure formation in zirconium alloys , 2015 .
[30] Arthur T. Motta,et al. Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding , 2015 .
[31] G. Was. Challenges to the use of ion irradiation for emulating reactor irradiation , 2015 .
[32] M. Preuss,et al. Identifying suboxide grains at the metal-oxide interface of a corroded Zr-1.0%Nb alloy using (S)TEM, transmission-EBSD and EELS. , 2015, Micron.
[33] L. Legras,et al. Microstructural Evolution of M5 TM7 Alloy Irradiated in PWRs up to High Fluences???Comparison With Other Zr-Based Alloys , 2015 .
[34] A. Motta,et al. Atom probe tomography study of alloying element distributions in Zr alloys and their oxides , 2013 .
[35] X. Feaugas,et al. Toward a better understanding of the hydrogen impact on the radiation induced growth of zirconium alloys , 2013 .
[36] E. Marquis,et al. Measuring Chemical Segregation at Grain Boundaries by Atom Probe Tomography , 2013, Microscopy and Microanalysis.
[37] W. Petry,et al. Heavy ion irradiation induced dislocation loops in AREVA’s M5® alloy , 2012 .
[38] V. Shishov,et al. Radiation Damage of E635 Alloy Under High Dose Irradiation in the VVER-1000 and BOR-60 Reactors , 2011 .
[39] V. Shishov. The Evolution of Microstructure and Deformation Stability in Zr–Nb–(Sn,Fe) Alloys Under Neutron Irradiation , 2010 .
[40] R. J. Daroda,et al. Characterization of density of biodiesel from soybean, sunflower, canola, and beef tallow in relation to temperature, using a digital density meter with a metrological point of view. , 2010 .
[41] G. Smith,et al. Initial observation of grain boundary solute segregation in a zirconium alloy (ZIRLO) by three-dimensional atom probe , 2009 .
[42] G. Smith,et al. Zirconium oxidation on the atomic scale. , 2009, Ultramicroscopy.
[43] K. Furuya,et al. Thickness measurements with electron energy loss spectroscopy , 2008, Microscopy research and technique.
[44] Gary S. Was,et al. Fundamentals of Radiation Materials Science: Metals and Alloys , 2007 .
[45] A. Motta,et al. Zirconium Alloys in Nuclear Applications , 2006 .
[46] I. Charit,et al. Creep behavior of niobium-modified zirconium alloys , 2006 .
[47] Yong Hwan Jeong,et al. Influence of Nb concentration in the α-matrix on the corrosion behavior of Zr- xNb binary alloys , 2003 .
[48] D. Seidman,et al. Measurement of the Gibbsian interfacial excess of solute at an interface of arbitrary geometry using three-dimensional atom probe microscopy , 2002 .
[49] R. Enrique,et al. Compositional patterning in immiscible alloys driven by irradiation , 2001 .
[50] Z. Q. Chen,et al. Evidence of defect associates in yttrium-stabilized zirconia ☆ , 2000 .
[51] Xin Guo,et al. Effect of niobia on the defect structure of yttria-stabilized zirconia , 1998 .
[52] A. Kozlov,et al. Influence of Neutron Irradiation on Dislocation Structure and Phase Composition of Zr-Base Alloys , 1996 .
[53] G. Smith,et al. Atom probe analysis of interfacial segregation , 1995 .
[54] S. Pyun,et al. Effect of composition and heat treatment on the microstructure and corrosion behavior of ZrNb alloys , 1994 .
[55] O. Woo,et al. Precipitation in Zr-2.5Nb During 10 MeV Electron Irradiation , 1994 .
[56] R. Egerton,et al. EELS log-ratio technique for specimen-thickness measurement in the TEM. , 1988, Journal of electron microscopy technique.
[57] M. Bamberger,et al. Determination of Fe solubility in αZr by Mössbauer spectroscopy , 1985 .
[58] Edward Hillner,et al. Corrosion of zirconium-base alloys: an overview , 1977 .
[59] A. Johnson,et al. Effect of Aging and Irradiation on the Corrosion of Zr-2.5 Wt% Nb , 1975 .