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Volumn 30, Issue 2, 2001, Pages 83-84

Discussion on Corrosion Transition Mechanism of Zircaloy

Author keywords

Corrosion; Phase transformation; Transition; Zircaloy

Indexed keywords


EID: 0348144516     PISSN: 1002185X     EISSN: None     Source Type: Journal    
DOI: None     Document Type: Article
Times cited : (7)

References (14)
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    • In-Situ Measurement of the Effect of LiOH on the Stability of Zircaloy-2 Surface Film in PWR Water
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  • 4
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    • Microstructure of Oxide Film Formed during the Waterside Corrosion of the Zircaloy-4 Cladding in Lithiated Environment
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    • Pecheur D, Godlewski J, Billot P et al. Microstructure of Oxide Film Formed during the Waterside Corrosion of the Zircaloy-4 Cladding in Lithiated Environment. In: Bradley E R and Sabol G P eds. Zirconium in the Nuclear Industry, Eleventh International Symposium[C], Philadelphia: America Society for Testing and Materials, 1996:94
    • (1996) Zirconium in the Nuclear Industry, Eleventh International Symposium , pp. 94
    • Pecheur, D.1    Godlewski, J.2    Billot, P.3
  • 5
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    • Contribution to the Understanding the Effect of the Water Chemistry on the Oxidation Kinetics of Zircaloy-4 Cladding
    • Bradley E R and Sabol G P eds., Philadelphia: America Society for Testing and Material
    • Pecheur D, Godlewski J, Peybernes J et al. Contribution to the Understanding the Effect of the Water Chemistry on the Oxidation Kinetics of Zircaloy-4 Cladding. In: Bradley E R and Sabol G P eds. Zirconium in the Nuclear Industry, Twelfth International Symposium[C], Philadelphia: America Society for Testing and Material, 2000:793
    • (2000) Zirconium in the Nuclear Industry, Twelfth International Symposium , pp. 793
    • Pecheur, D.1    Godlewski, J.2    Peybernes, J.3
  • 6
    • 0006240813 scopus 로고    scopus 로고
    • The Effect of Water Chemistry on the Corrosion Behavior of Zirconium Alloys
    • Zhou Bangxin, Li Qiang, Huang Qiang et al. The Effect of Water Chemistry on the Corrosion Behavior of Zirconium Alloys [J]. Nuclear Power Engineering, 2000;21(5):439
    • (2000) Nuclear Power Engineering , vol.21 , Issue.5 , pp. 439
    • Zhou, B.1    Li, Q.2    Huang, Q.3
  • 7
    • 0000915131 scopus 로고
    • Examination of the Corrosion Mechanism of Zirconium Alloys
    • Grade A M and Bradley E R eds., Philadelphia: America Society for Testing and Materials
    • Beie H-J, Mitwalsky A, Garzarolli F et al. Examination of the Corrosion Mechanism of Zirconium Alloys. In: Grade A M and Bradley E R eds. Zirconium in the Nuclear Industry Tenth International Symposium [C], Philadelphia: America Society for Testing and Materials, 1994:615
    • (1994) Zirconium in the Nuclear Industry Tenth International Symposium , pp. 615
    • Beie, H.-J.1    Mitwalsky, A.2    Garzarolli, F.3
  • 9
    • 0030289361 scopus 로고    scopus 로고
    • Microstructure of Oxides on Zircaloy-4, 1.0 Nb Zircaloy-4, and Zircaloy-2 Formed on 10.3 MPa Steam at 673 K
    • Bradley E R and Sabol G P eds., Philadelphia: America Society for Testing and Materials
    • Anada H, Takeda K. Microstructure of Oxides on Zircaloy-4, 1.0 Nb Zircaloy-4, and Zircaloy-2 Formed on 10.3 MPa Steam at 673 K. In: Bradley E R and Sabol G P eds. Zirconium in the Nuclear Industry, Eleventh International Symposium [C], Philadelphia: America Society for Testing and Materials, 1996:35
    • (1996) Zirconium in the Nuclear Industry, Eleventh International Symposium , pp. 35
    • Anada, H.1    Takeda, K.2
  • 10
    • 0001088426 scopus 로고
    • Oxide Growth Mechanism on Zircaloy
    • Eucken C M and Grade A M eds, Philadelphia; America Society for Testing and Materials
    • Garzarolli F, Seidsl H, Tricot R et al. Oxide Growth Mechanism on Zircaloy. In: Eucken C M and Grade A M eds, Zirconivm in the Nuclear Industry, Ninth International Symposium[C], Philadelphia; America Society for Testing and Materials, 1991:395
    • (1991) Zirconivm in the Nuclear Industry, Ninth International Symposium , pp. 395
    • Garzarolli, F.1    Seidsl, H.2    Tricot, R.3
  • 11
    • 33745501263 scopus 로고
    • Oxidation of Zircaloy-2 in Air from 500°C to 800°C
    • Guan H-G, Wu W-T, Shen J-N and Li T-F eds., Shengyang, China: Liaoning Science and Technology Publishing House
    • Zhou B-X, Jiang Y-R. Oxidation of Zircaloy-2 in Air from 500°C to 800°C. In: Guan H-G, Wu W-T, Shen J-N and Li T-F eds. High Temperature Corrosion and Protection, Proc Inter Sym[C], Shengyang, China: Liaoning Science and Technology Publishing House, 1991:121
    • (1991) High Temperature Corrosion and Protection, Proc Inter Sym , pp. 121
    • Zhou, B.-X.1    Jiang, Y.-R.2
  • 12
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    • How the Tetragonal Zirconia is Stabilized in the Oxide Scale That is Formed on a Zirconium Alloy Corroded at 400°C in Steam
    • Bradley E R and Sabol G P eds., Philadelphia: Ameria Society for Testing and Materials
    • Godlewski J. How the Tetragonal Zirconia is Stabilized in the Oxide Scale That is Formed on a Zirconium Alloy Corroded at 400°C in Steam. In:Bradley E R and Sabol G P eds. Zirconium in the Nuclear Industry, Tenth International Symposium[C], Philadelphia: Ameria Society for Testing and Materials, 1994:663
    • (1994) Zirconium in the Nuclear Industry, Tenth International Symposium , pp. 663
    • Godlewski, J.1
  • 13
    • 0032636004 scopus 로고    scopus 로고
    • Crystallization and Degradation of Zirconium Oxide in Various pH Solution
    • Kim Y-S, Kwon S-C. Crystallization and Degradation of Zirconium Oxide in Various pH Solution[J]. J Nucl Mat, 1999;270:165
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    • Kim, Y.-S.1    Kwon, S.-C.2
  • 14
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    • Behaviors of Lithium and Boron in Irradiated and Unirradiated Oxides Formed on Zircaloy-4 Claddings
    • Bradley E R and Sabol G P eds., America Society fo Testing and Materials
    • Kido T. Behaviors of Lithium and Boron in Irradiated and Unirradiated Oxides Formed on Zircaloy-4 Claddings. In: Bradley E R and Sabol G P eds. Zirconium in the Nuclear Industry, Twlfth International Symposium [C], America Society fo Testing and Materials, 2000:773
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    • Kido, T.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.