메뉴 건너뛰기




Volumn 60, Issue 20, 2012, Pages 7132-7149

How the crystallography and nanoscale chemistry of the metal/oxide interface develops during the aqueous oxidation of zirconium cladding alloys

Author keywords

Atom probe tomography (APT); Corrosion mechanisms; Metal scale interface; Transmission electron microscopy (TEM); Zirconium alloys

Indexed keywords

AQUEOUS CORROSION; AQUEOUS OXIDATION; ASSEMBLY COMPONENT; ATOM-PROBE TOMOGRAPHY; CLADDING ALLOYS; CORROSION MECHANISMS; DIFFERENT STRUCTURE; FUEL CLADDING; KINETIC TRANSITION; METAL OXIDE INTERFACE; NANO SCALE; OXIDATION KINETICS; OXIDATION PROCESS; OXIDE LAYER; PROTECTIVE LAYERS; SYSTEMATIC INVESTIGATIONS; TRANSMISSION ELECTRON MICROSCOPY TEM;

EID: 84868208029     PISSN: 13596454     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.actamat.2012.09.021     Document Type: Article
Times cited : (157)

References (92)
  • 2
    • 33744816490 scopus 로고    scopus 로고
    • ZIRLO™ - An alloy development success
    • Rudling P, Kammenzind B, editors ASTM STP 1467. West Conshohocken, PA: ASTM International
    • Sabol GP. ZIRLO™ - An alloy development success. In: Rudling P, Kammenzind B, editors. Zirconium in the nuclear industry: fourteenth international symposium, ASTM STP 1467. West Conshohocken, PA: ASTM International; 2005.
    • (2005) Zirconium in the Nuclear Industry: Fourteenth International Symposium
    • Sabol, G.P.1
  • 3
    • 0000882280 scopus 로고
    • Oxidation of zirconium and its alloys
    • M.G. Fontana, R.W. Staehle, Plenum New York
    • B. Cox Oxidation of zirconium and its alloys M.G. Fontana, R.W. Staehle, Advances in corrosion science and technology 1976 Plenum New York
    • (1976) Advances in Corrosion Science and Technology
    • Cox, B.1
  • 4
    • 80052559162 scopus 로고
    • Zirconium alloy performance in light water reactors: A review of UK and Scandinavian experience
    • Garde AM, Bradley ER, editors West Conshohocken, PA: ASTM International
    • Pickman DO. Zirconium alloy performance in light water reactors: a review of UK and Scandinavian experience. In: Garde AM, Bradley ER, editors. Zirconium in the nuclear industry: tenth international symposium, ASTM STP 1245. West Conshohocken, PA: ASTM International; 1994.
    • (1994) Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245
    • Pickman, D.O.1
  • 9
    • 84868202448 scopus 로고    scopus 로고
    • 13C corrosion: environments and industries
    • Lemaignan C. ASM handbook 2006; 13C corrosion: environments and industries; 2006. p. 415.
    • (2006) ASM Handbook 2006 , pp. 415
    • Lemaignan, C.1
  • 29
    • 0030285164 scopus 로고    scopus 로고
    • Long-term in situ corrosion investigation of Zr alloys in simulated PWR environment by electrochemical measurements
    • E.R. Bradley, G.P. Sabol, ASTM International West Conshohocken, PA
    • H. Göhr, J. Schaller, H. Ruhmann, and F. Garzarolli Long-term in situ corrosion investigation of Zr alloys in simulated PWR environment by electrochemical measurements E.R. Bradley, G.P. Sabol, Zirconium in the nuclear industry: eleventh international symposium, ASTM STP 1295 1996 ASTM International West Conshohocken, PA
    • (1996) Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295
    • Göhr, H.1    Schaller, J.2    Ruhmann, H.3    Garzarolli, F.4
  • 34
    • 0030289887 scopus 로고    scopus 로고
    • Microstructure of oxide films formed during the waterside corrosion of the Zircaloy-4 cladding in lithiated environment
    • E.R. Bradley, G.P. Sabol, ASTM International West Conshohocken, PA
    • D. Pêcheur, J. Godlewski, P. Billot, and J. Thomazet Microstructure of oxide films formed during the waterside corrosion of the Zircaloy-4 cladding in lithiated environment E.R. Bradley, G.P. Sabol, Zirconium in the nuclear industry: eleventh international symposium, ASTM STP 1295 1996 ASTM International West Conshohocken, PA
    • (1996) Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295
    • Pêcheur, D.1    Godlewski, J.2    Billot, P.3    Thomazet, J.4
  • 36
    • 0030289361 scopus 로고    scopus 로고
    • Microstructure of oxides on Zircaloy-4, 1.0Nb Zircaloy-4, and Zircaloy-2 formed in 10.3-MPa steam at 673 K
    • Bradley ER, Sabol GP, editors West Conshohocken, PA: ASTM International
    • Anada H, Takeda K. Microstructure of oxides on Zircaloy-4, 1.0Nb Zircaloy-4, and Zircaloy-2 formed in 10.3-MPa steam at 673 K. In: Bradley ER, Sabol GP, editors. Zirconium in the nuclear industry: eleventh international symposium, ASTM STP 1295. West Conshohocken, PA: ASTM International; 1996.
    • (1996) Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295
    • Anada, H.1    Takeda, K.2
  • 37
    • 8844221532 scopus 로고    scopus 로고
    • The microstructural characterization of factors which determin the degradation behaviour of Zircaloy-4
    • S.B. Newcomb, J.A. Little, Henry Ling Dorest
    • D.T. Foord, and S.B. Newcomb The microstructural characterization of factors which determin the degradation behaviour of Zircaloy-4 S.B. Newcomb, J.A. Little, Microscopy of oxidation 3 1996 Henry Ling Dorest
    • (1996) Microscopy of Oxidation 3
    • Foord, D.T.1    Newcomb, S.B.2
  • 51
    • 0026381514 scopus 로고
    • Raman spectroscopy study of the tetragonal-to-monoclinic transition in zirconium oxide scales and determination of overall oxygen diffusion by nuclear microanalysis of O18
    • C.M. Eucken, A.M. Garde, ASTM International West Conshohocken, PA
    • J. Godlewski, P. Gros, M. Lambertin, J.F. Wadier, and H. Weidinger Raman spectroscopy study of the tetragonal-to-monoclinic transition in zirconium oxide scales and determination of overall oxygen diffusion by nuclear microanalysis of O18 C.M. Eucken, A.M. Garde, Zirconium in the nuclear industry: ninth international symposium, ASTM STP 1132 1991 ASTM International West Conshohocken, PA
    • (1991) Zirconium in the Nuclear Industry: Ninth International Symposium, ASTM STP 1132
    • Godlewski, J.1    Gros, P.2    Lambertin, M.3    Wadier, J.F.4    Weidinger, H.5
  • 53
    • 0000915132 scopus 로고
    • How the tetragonal zirconia is stabilized in the oxide scale that if formed on a zirconium alloy corroded at 400°C in steam
    • A.M. Garde, E.R. Bradley, ASTM International West Conshohocken, PA
    • J. Godlewski How the tetragonal zirconia is stabilized in the oxide scale that if formed on a zirconium alloy corroded at 400°C in steam A.M. Garde, E.R. Bradley, Zirconium in the nuclear industry: tenth international symposium, ASTM STP 1245 1994 ASTM International West Conshohocken, PA
    • (1994) Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245
    • Godlewski, J.1
  • 55
    • 0013134787 scopus 로고
    • Precipitate behavior in Zircaloy-2 oxide-films and its relevance to corrosion-resistance
    • C.M. Eucken, A.M. Garde, ASTM International West Conshohocken, PA
    • T. Kubo, and M. Uno Precipitate behavior in Zircaloy-2 oxide-films and its relevance to corrosion-resistance C.M. Eucken, A.M. Garde, Zirconium in the nuclear industry: ninth international symposium, ASTM STP 1132 1990 ASTM International West Conshohocken, PA
    • (1990) Zirconium in the Nuclear Industry: Ninth International Symposium, ASTM STP 1132
    • Kubo, T.1    Uno, M.2
  • 62
    • 0343254812 scopus 로고    scopus 로고
    • Oxide characteristics and corrosion and hydrogen uptake in Zr-2.5 Nb CANDU pressure tubes
    • Bradley ER, Sabol GP, editors West Conshohocken, PA: ASTM International
    • Warr BD, Heide PAWVD, Maruire MA. Oxide characteristics and corrosion and hydrogen uptake in Zr-2.5 Nb CANDU pressure tubes. In: Bradley ER, Sabol GP, editors. Zirconium in the nuclear industry: eleventh international symposium, ASTM STP 1295. West Conshohocken, PA: ASTM International; 1996.
    • (1996) Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295
    • Warr, B.D.1    Pawvd, H.2    Maruire, M.A.3
  • 70
    • 10644286254 scopus 로고
    • Instabilities in the oxidation behaviour of Zircaloy-4
    • S.B. Newcomb, M.J. Bennett, The Institute of Materials London
    • D.T. Foord, and S.B. Newcomb Instabilities in the oxidation behaviour of Zircaloy-4 S.B. Newcomb, M.J. Bennett, Microscopy of oxidation-2 1993 The Institute of Materials London
    • (1993) Microscopy of oxidation-2
    • Foord, D.T.1    Newcomb, S.B.2
  • 79
    • 0009915273 scopus 로고
    • Corrosion behaviour of Zircaloy-4 sheets produced under various hot-rolling and annealing conditions
    • A.M. Garde, E.R. Bradley, American Society for Testing and Materials West Conshohocken, PA
    • H. Anada, K. Nomoto, and Y. Shida Corrosion behaviour of Zircaloy-4 sheets produced under various hot-rolling and annealing conditions A.M. Garde, E.R. Bradley, Zirconium in the nuclear industry: tenth international symposium, ASTM STP 1245 1994 American Society for Testing and Materials West Conshohocken, PA
    • (1994) Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245
    • Anada, H.1    Nomoto, K.2    Shida, Y.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.