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Volumn 245, Issue 2-3, 1997, Pages 152-160

High pressure oxidation of sponge-Zr in steam/hydrogen mixtures

Author keywords

[No Author keywords available]

Indexed keywords

COMPOSITION EFFECTS; HELIUM; HYDRIDES; HYDROGEN; MIXTURES; MORPHOLOGY; OXIDATION; OXIDES; OXYGEN; PRESSURE EFFECTS; REACTION KINETICS; STEAM;

EID: 0031168738     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0022-3115(97)00018-4     Document Type: Article
Times cited : (12)

References (26)
  • 6
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    • E. Hillner, Corrosion of zirconium-base alloys: An overview, Zirconium in the Nuclear Industry, vol. 633, ASTM STP, 1977, p. 211.
    • (1977) Zirconium in the Nuclear Industry , vol.633 , pp. 211
    • Hillner, E.1
  • 7
    • 0019899148 scopus 로고
    • Waterside corrosion of Zircaloy-clad fuel rods in a PWR environment
    • ASTM STP
    • F. Garzarolli et al., Waterside corrosion of Zircaloy-clad fuel rods in a PWR environment, Zirconium in the Nuclear Industry, vol.754, ASTM STP, 1982, p. 430.
    • (1982) Zirconium in the Nuclear Industry , vol.754 , pp. 430
    • Garzarolli, F.1
  • 8
    • 0343254692 scopus 로고
    • Correlation between 400°C steam corrosion behavior, heat treatment and microstructure of Zircaloy-4 tubing
    • ASTM STP
    • T. Thorvaldsson et al., Correlation between 400°C steam corrosion behavior, heat treatment and microstructure of Zircaloy-4 tubing, Zirconium in the Nuclear Industry, vol. 1023, ASTM STP, 1989, p. 128.
    • (1989) Zirconium in the Nuclear Industry , vol.1023 , pp. 128
    • Thorvaldsson, T.1
  • 9
    • 0001429214 scopus 로고
    • Development of a cladding alloy for high burnup
    • ASTM STP
    • G.P. Sabol et al., Development of a cladding alloy for high burnup, Zirconium in the Nuclear Industry, vol. 1023, ASTM STP, 1989, p. 227.
    • (1989) Zirconium in the Nuclear Industry , vol.1023 , pp. 227
    • Sabol, G.P.1
  • 14
    • 0003478633 scopus 로고
    • IAEA, Suppl., International Atomic Energy Agency, Vienna
    • D.L. Douglass, The Metallurgy of Zirconium, IAEA, Suppl., International Atomic Energy Agency, Vienna, 1971.
    • (1971) The Metallurgy of Zirconium
    • Douglass, D.L.1
  • 21
    • 85170061472 scopus 로고
    • Corrosion and failure characteristics of zirconium alloys in high-pressure steam in the temperature range 400 to 500°C
    • ASTM STP
    • A.B. Johnson Jr., Corrosion and failure characteristics of zirconium alloys in high-pressure steam in the temperature range 400 to 500°C, Applications-related Phenomena for Zirconium and its Alloys, vol. 458, ASTM STP, 1969, p. 271.
    • (1969) Applications-related Phenomena for Zirconium and Its Alloys , vol.458 , pp. 271
    • Johnson A.B., Jr.1
  • 22
    • 85169426339 scopus 로고
    • The development of the Zircaloys
    • ASTM STP
    • S. Kass, The development of the Zircaloys, Corrosion of Zirconium Alloys, vol. 368, ASTM STP, 1963, p. 3.
    • (1963) Corrosion of Zirconium Alloys , vol.368 , pp. 3
    • Kass, S.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.