메뉴 건너뛰기




Volumn , Issue 1354, 2000, Pages 641-657

Microstructural aspects of corrosion and hydrogen ingress in Zr-2.5Nb

Author keywords

[No Author keywords available]

Indexed keywords

BINARY ALLOYS; COLD WORKING; CORROSION; CRYSTAL MICROSTRUCTURE; HYDROGEN EMBRITTLEMENT; METAL EXTRUSION; METALLOGRAPHIC MICROSTRUCTURE; NEUTRON IRRADIATION; NUCLEAR REACTORS; RADIATION DAMAGE; STRESS RELIEF; TUBES (COMPONENTS);

EID: 0033881794     PISSN: 10403094     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/stp14321s     Document Type: Conference Paper
Times cited : (64)

References (15)
  • 3
    • 0030217363 scopus 로고    scopus 로고
    • Corrosion Response of Pre-irradiated Zr-2.5Nb Pressure Tube Material
    • D. S. Gelles, R. K. Nanstad, A. S. Kumar, and E. A. Little, Eds., American Society for Testing and Materials, West Conshohocken, PA
    • Urbanic, V. F. and Griffiths, M., "Corrosion Response of Pre-irradiated Zr-2.5Nb Pressure Tube Material," Effects of Radiation on Materials: 17th International Symposium, ASTM STP 1270, D. S. Gelles, R. K. Nanstad, A. S. Kumar, and E. A. Little, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1996, pp. 1088-1106.
    • (1996) Effects of Radiation on Materials: 17th International Symposium, ASTM STP 1270 , pp. 1088-1106
    • Urbanic, V.F.1    Griffiths, M.2
  • 4
    • 0030284734 scopus 로고    scopus 로고
    • Evolution of Microstructure in Zirconium Alloys during Irradiation
    • E. R. Bradley and G. P. Sabol, Eds., American Society for Testing and Materials, West Conshohocken, PA, Also as AECL Report RC-1477
    • Griffiths, M., Mecke, J. F., and Winegar, J. E., "Evolution of Microstructure in Zirconium Alloys during Irradiation," Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295, E. R. Bradley and G. P. Sabol, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1996, pp. 580-602. Also as AECL Report RC-1477.
    • (1996) Zirconium in the Nuclear Industry: Eleventh International Symposium, ASTM STP 1295 , pp. 580-602
    • Griffiths, M.1    Mecke, J.F.2    Winegar, J.E.3
  • 7
    • 0342820054 scopus 로고
    • The Physical Metallurgy of Zirconium
    • IAEA, Vienna
    • Douglas, D. L., "The Physical Metallurgy of Zirconium," International Atomic Review, IAEA, Vienna, 1971.
    • (1971) International Atomic Review
    • Douglas, D.L.1
  • 8
    • 0342385350 scopus 로고
    • Growth and Characterization of Oxide Films on Zirconium-Niobium Alloys
    • A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, Philadelphia, PA
    • Urbanic, V. F., Chan, P. K., Khatamian, D., and Woo, O. T., "Growth and Characterization of Oxide Films on Zirconium-Niobium Alloys," Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245, A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, Philadelphia, PA, 1994, pp. 116-130.
    • (1994) Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245 , pp. 116-130
    • Urbanic, V.F.1    Chan, P.K.2    Khatamian, D.3    Woo, O.T.4
  • 9
    • 85169428951 scopus 로고
    • Neutron Irradiation and Cold Work Effects on Zircaloy-2 Corrosion and Hydrogen Pickup
    • Burns, W. A. and Maffei, H. P., "Neutron Irradiation and Cold Work Effects on Zircaloy-2 Corrosion and Hydrogen Pickup," ASTM STP 368, 1963, pp. 101-117.
    • (1963) ASTM STP 368 , pp. 101-117
    • Burns, W.A.1    Maffei, H.P.2
  • 10
    • 0008602902 scopus 로고
    • Oxidation and Deuterium Uptake of Zr-2.5Nb Pressure Tubes in CANDU-PHW Reactors
    • L. F. P Van Swam and C. M. Eucken, Eds., American Society for Testing and Materials, Philadelphia, PA
    • Urbanic, V. F., Warr, B. D., Manolescu, A., Chow, C. K., and Shanahan, M. W., "Oxidation and Deuterium Uptake of Zr-2.5Nb Pressure Tubes in CANDU-PHW Reactors," Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023, L. F. P Van Swam and C. M. Eucken, Eds., American Society for Testing and Materials, Philadelphia, PA, 1989, pp. 20-34.
    • (1989) Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023 , pp. 20-34
    • Urbanic, V.F.1    Warr, B.D.2    Manolescu, A.3    Chow, C.K.4    Shanahan, M.W.5
  • 11
    • 0030291865 scopus 로고    scopus 로고
    • Effects of Thermomechanical Processing on In-reactor Corrosion and Post-irradiation Mechanical Properties of Zircaloy-2
    • E. R. Bradley and G. P. Sabol, Eds., American Society for Testing and Materials, West Conshohocken, PA
    • Huang, P. Y., Mahmood, S. T., and Adamson, R. B., "Effects of Thermomechanical Processing on In-reactor Corrosion and Post-irradiation Mechanical Properties of Zircaloy-2," Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1295, E. R. Bradley and G. P. Sabol, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1996, pp. 726-757.
    • (1996) Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1295 , pp. 726-757
    • Huang, P.Y.1    Mahmood, S.T.2    Adamson, R.B.3
  • 12
    • 0015403180 scopus 로고
    • The Stability of Precipitates in an Irradiation Environment
    • Nelson, R. S., Hudson, J. A., and Mazey, D. J, "The Stability of Precipitates in an Irradiation Environment," Journal of Nuclear Materials, Vol. 44, 1972, pp. 318-330.
    • (1972) Journal of Nuclear Materials , vol.44 , pp. 318-330
    • Nelson, R.S.1    Hudson, J.A.2    Mazey, D.J.3
  • 13
    • 0019689183 scopus 로고
    • Precipitation in Zr-2.5 wt% Nb during Neutron Irradiation in Phase Stability during Irradiation
    • J. R. Holand, L. K. Mansur, and D. I. Potter, Eds., The Metallurgical Society of AIME, Pittsburgh, PA
    • Coleman, C. E., Gilbert, R. W., Carpenter, G. J. C., and Weatherley, G. C., "Precipitation in Zr-2.5 wt% Nb During Neutron Irradiation in Phase Stability During Irradiation," J. R. Holand, L. K. Mansur, and D. I. Potter, Eds., from Phase Stability During Irradiation, The Metallurgical Society of AIME, Pittsburgh, PA, 1981, pp. 587-599.
    • (1981) Phase Stability during Irradiation , pp. 587-599
    • Coleman, C.E.1    Gilbert, R.W.2    Carpenter, G.J.C.3    Weatherley, G.C.4
  • 14
    • 0016569910 scopus 로고
    • Point Defect Behavior in Irradiated Materials
    • Heald, P. T. and Speight, M. V., "Point Defect Behavior in Irradiated Materials," Acta Metallurgica, Vol. 23, 1975, p. 1389.
    • (1975) Acta Metallurgica , vol.23 , pp. 1389
    • Heald, P.T.1    Speight, M.V.2
  • 15


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.