최소 단어 이상 선택하여야 합니다.
최대 10 단어까지만 선택 가능합니다.
다음과 같은 기능을 한번의 로그인으로 사용 할 수 있습니다.
NTIS 바로가기Corrosion science, v.157, 2019년, pp.180 - 188
Kim, Taeho (Department of Engineering Physics, University of Wisconsin-Madison) , Kim, Seunghyun (Authorized Nuclear Inspection Department, Korea Institute of Materials Science (KIMS)) , Lee, Yunju (Department of Nuclear Engineering, School of Mechanical, Aerospace, and Nuclear Engineering, Ulsan National Institute of Science and Technology (UNIST)) , Kim, Namdong (Beam Line Division, Pohang Accelerator Laboratory, POSTECH) , Bahn, Chi Bum (School of Mechanical Engineering, Pusan National University) , Couet, Adrien (Department of Engineering Physics, University of Wisconsin-Madison) , Kim, Ji Hyun (Department of Nuclear Engineering, School of Mechanical, Aerospace, and Nuclear Engineering, Ulsan National Institute of Science and Technology (UNIST))
Abstract The corrosion behavior of zirconium alloy was investigated using synchrotron scanning transmission X-ray microscopy and X-ray absorption spectroscopy. Scanning transmission X-ray micrographs showed different electronic structures at the oxide/metal interface of Zr–Nb–Sn alloy a...
Acta Mater. Zinkle 61 735 2013 10.1016/j.actamat.2012.11.004 Materials challenges in nuclear energy
Annu. Rev. Mater. Res. Motta 45 311 2015 10.1146/annurev-matsci-070214-020951 Corrosion of zirconium alloys used for nuclear fuel cladding
J. Nucl. Mater. Platt 456 415 2015 10.1016/j.jnucmat.2014.09.072 A study into stress relaxation in oxides formed on zirconium alloys
J. Am. Ceram. Soc. Quintard 85 1745 2002 10.1111/j.1151-2916.2002.tb00346.x Comparative latticedynamical study of the Raman spectra of monoclinic and tetragonal phases of zirconia and Hafnia
J. Nucl. Mater. Parise 256 35 1998 10.1016/S0022-3115(98)00045-2 Modelling of the mechanical behavior of the metal-oxide system during Zr alloy oxidation
Corros. Sci. Meng 53 2558 2011 10.1016/j.corsci.2011.04.013 Stress corrosion cracking of uni-directionally cold worked 316NG stainless steel in simulated PWR primary water with various dissolved hydrogen concentrations
Corros. Sci. Xu 97 115 2015 10.1016/j.corsci.2015.04.021 The effects of dissolved hydrogen on the corrosion behavior of Alloy 182 in simulated primary water
Corros. Sci. Qiu 53 1983 2011 10.1016/j.corsci.2011.02.020 Effect of dissolved hydrogen on the electrochemical behaviour of Alloy 600 in simulated PWR primary water at 290°C
Corros. Sci. Ziemniak 48 498 2006 10.1016/j.corsci.2005.01.006 Corrosion behavior of NiCrFe Alloy 600 in high temperature, hydrogenated water
Corrosion Andresen 64 707 2008 10.5006/1.3278508 Effects of hydrogen on stress corrosion crack growth rate of nickel alloys in high-temperature water
Corros. Sci. Kim 131 235 2018 10.1016/j.corsci.2017.11.026 Influence of dissolved hydrogen on the early stage corrosion behavior of zirconium alloys in simulated light water reactor coolant conditions
Frankel vol. 17 4200 2013 The effect of Sn on corrosion mechanisms in advanced Zr-cladding for pressurised water reactors
Acta Mater. Garner 80 159 2014 10.1016/j.actamat.2014.07.062 The microstructure and microtexture of zirconium oxide films stiudied by transmission electron backscatter diffraction and automated crystal orientation mapping with transmission electron microscopy
Acta Mater. Qin 55 1695 2007 10.1016/j.actamat.2006.10.030 Tetragonal phase stability in ZrO2 film formed on zirconium alloys and its effects on corrosion resistance
J. Nucl. Mater. Yilmazbayhan 349 265 2006 10.1016/j.jnucmat.2005.10.012 Transmission electron microscopy examination of oxide layers formed on Zr alloys
J. Nucl. Mater. Kim 374 204 2008 10.1016/j.jnucmat.2007.08.003 Evaluation of pre-transition oxide on Zr-0.4 Nb alloy by using the HVEM
Anada 35 1996 Zirconium in the Nuclear Industry: 11th International Symposium, ASTM STP 1295 Microstructure of oxides on zircaloy-4, 1.0Nb zircaloy-4, and zircaloy-2 formed in 10.3-MPa steam at 673 K
Acta Mater. Ni 60 7132 2012 10.1016/j.actamat.2012.09.021 How the crystallography and nanoscale chemistry of the metal/oxide interface develops during the aqueous oxidation of zirconium cladding alloys
Acta Mater. Garner 99 259 2015 10.1016/j.actamat.2015.08.005 The effect of Sn concentration on oxide texture and microstructure formation in zirconium alloys
J. Nucl. Mater. Garner 484 347 2017 10.1016/j.jnucmat.2016.10.037 The effect of substrate texture and oxidation temperature on oxide texture development in zirconium alloys
Micron Hu 69 35 2015 10.1016/j.micron.2014.10.004 Identifying suboxide grains at the metal-oxide interface of a corroded Zr-1.0%Nb alloy using (S)TEM, transmission-EBSD and EELS
J. Electron Spectros. Relat. Phenomena Kikas 156158 303 2007 10.1016/j.elspec.2006.11.031 Effect of phase composition on X-ray absorption spectra of ZrO2 thin films
J. Nucl. Mater. Couet 452 614 2014 10.1016/j.jnucmat.2014.05.047 Microbeam X-ray absorption near-edge spectroscopy study of the oxidation of Fe and Nb in zirconium alloy oxide layers
Adv. Mater. Lett. Sharma 7 17 2016 10.5185/amlett.2016.6136 Electronic structure study and dielectric properties of amorphous ZrO2 and HfO2
Chem. Phys. Lett. Sharma 592 85 2014 10.1016/j.cplett.2013.12.012 Monoclinic to tetragonal phase transition in ZrO 2 thin films under swift heavy ion irradiation: structural and electronic structure study
Phys. Rev. B McComb 54 7094 1996 10.1103/PhysRevB.54.7094 Bonding and electronic structure in zirconia pseudopolymorphs investigated by electron energy-loss spectroscopy
Corros. Sci. Ye 106 249 2016 10.1016/j.corsci.2016.02.010 The high-temperature corrosion of Hastelloy N alloy (UNS N10003) in molten fluoride salts analysed by STXM, XAS, XRD, SEM, EPMA, TEM/EDS
Talanta Degueldre 75 402 2008 10.1016/j.talanta.2007.11.052 Zircaloy-2 secondary phase precipitate analysis by X-ray microspectroscopy
Corros. Sci. Kim 99 134 2015 10.1016/j.corsci.2015.06.034 Phase transformation of oxide film in zirconium alloy in high temperature hydrogenated water
J. Am. Ceram. Soc. Lei 63 2359 2002 10.1111/j.1151-2916.2002.tb00460.x Segregation effects at grain boundaries in fluoritestructured ceramics
J. Phys. Condens. Matter Harvey 18 2181 2006 10.1088/0953-8984/18/7/007 A systematic study of the oxygen K edge in the cubic and less common monoclinic phases of the rare earth oxides (Ho, Er, Tm, Yb) by electron energy loss spectroscopy
Adv. Eng. Mater. Nicholls 17 211 2015 10.1002/adem.201400133 Crystal structure of the ZrO phase at zirconium/zirconium oxide interfaces
Surf. Coat. Technol. Roddatis 151-152 63 2002 10.1016/S0257-8972(01)01576-6 The structure of thin zirconia films obtained by self-assembled monolayer mediated deposition: TEM and HREM study
Corros. Sci. Hulme 105 202 2016 10.1016/j.corsci.2016.01.018 An X-ray absorption near-edge structure (XANES) study of the Sn L3 edge in zirconium alloy oxide films formed during autoclave corrosion
J. Nucl. Mater. Annand 465 390 2015 10.1016/j.jnucmat.2015.06.022 Utilising DualEELS to probe the nanoscale mechanisms of the corrosion of Zircaloy-4 in 350°C pressurised water
J. Nucl. Mater. Kurpaska 476 56 2016 10.1016/j.jnucmat.2016.04.038 Study of sub-oxide phases at the metal-oxide interface in oxidized pure zirconium and Zr-1.0% Nb alloy by using SEM/FIB/EBSD and EDS techniques
J. Nucl. Mater. de Gabory 462 304 2015 10.1016/j.jnucmat.2015.03.043 EELS and atom probe tomography study of the evolution of the metal/oxide interface during zirconium alloy oxidation
Corros. Sci. Couet 100 73 2015 10.1016/j.corsci.2015.07.003 The coupled current charge compensation model for zirconium alloy fuel cladding oxidation: I. Parabolic oxidation of zirconium alloys
*원문 PDF 파일 및 링크정보가 존재하지 않을 경우 KISTI DDS 시스템에서 제공하는 원문복사서비스를 사용할 수 있습니다.
※ AI-Helper는 부적절한 답변을 할 수 있습니다.