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Volumn 1295, Issue , 1996, Pages 407-430

Effects of hydride precipitate localization and neutron fluence on the ductility of irradiated zircaloy-4

Author keywords

Composite; Ductility; Hydride localization; Hydride volume fraction; Hydriding; Mechanical properties; Radiation damage; Zircaloy 4

Indexed keywords

COMPOSITION EFFECTS; DUCTILITY; HYDRIDES; HYDROGEN EMBRITTLEMENT; NEUTRON IRRADIATION; NUCLEAR FUEL CLADDING; PRECIPITATION (CHEMICAL); PRESSURIZED WATER REACTORS; RADIATION DAMAGE; TENSILE TESTING; THERMAL EFFECTS; VOLUME FRACTION;

EID: 5544310313     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/stp16183s     Document Type: Article
Times cited : (85)

References (26)
  • 1
    • 0342819182 scopus 로고
    • Effects of Irradiation and Hydriding on the Mechanical Properties of Zircaloy-4 at High Fluence
    • L. F. P. Van Swam and C. M. Eucken, Eds., American Society for Testing and Materials, West Conshohocken, PA
    • Garde, A. M., "Effects of Irradiation and Hydriding on the Mechanical Properties of Zircaloy-4 at High Fluence," 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, West Conshohocken, PA, 1989, pp. 548-569.
    • (1989) Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023 , pp. 548-569
    • Garde, A.M.1
  • 7
    • 0002355665 scopus 로고
    • Chapter 3 R. T. DeHoff and F. N. Rhines, Eds., McGraw-Hill, New York
    • Hilliard, J. E., Chapter 3 in Quantitative Microscopy, R. T. DeHoff and F. N. Rhines, Eds., McGraw-Hill, New York, 1968, pp. 45-76.
    • (1968) Quantitative Microscopy , pp. 45-76
    • Hilliard, J.E.1
  • 8
    • 0003702973 scopus 로고
    • Chapter 25 Pergamon Press, Elmsford, NY
    • Ashby, M. F. and Jones, D. R. H., Chapter 25 in Engineering Materials 2, Pergamon Press, Elmsford, NY, 1992, pp. 241-254.
    • (1992) Engineering Materials 2 , pp. 241-254
    • Ashby, M.F.1    Jones, D.R.H.2
  • 9
    • 85168662828 scopus 로고
    • Deformation and Fracture Properties of Neutron-Irradiated Recrystallized Zircaloy-2 Cladding under Uniaxial Tension
    • R. B. Adamson and L. F. P. Van Swam, Eds., American Society for Testing and Materials, West Conshohocken, PA
    • Yasuda, T., Nakatsuka, M., and Yamashita, K., "Deformation and Fracture Properties of Neutron-Irradiated Recrystallized Zircaloy-2 Cladding Under Uniaxial Tension," Zirconium in Nuclear Industry: Seventh International Symposium, ASTM STP 939, R. B. Adamson and L. F. P. Van Swam, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1987, pp. 734-747.
    • (1987) Zirconium in Nuclear Industry: Seventh International Symposium, ASTM STP 939 , pp. 734-747
    • Yasuda, T.1    Nakatsuka, M.2    Yamashita, K.3
  • 11
    • 84896923582 scopus 로고
    • Effect of Irradiation at 588 K on Mechanical Properties and Deformation Behavior of Zirconium Alloy Strip
    • R. B. Adamson and L. F. P. Van Swam, Eds., American Society for Testing and Materials, West Conshohocken, PA
    • Morize, P., Baicry, J., and Mardon, J. P., "Effect of Irradiation at 588 K on Mechanical Properties and Deformation Behavior of Zirconium Alloy Strip," Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939, R. B. Adamson and L. F. P. Van Swam, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1987, pp. 101-119.
    • (1987) Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939 , pp. 101-119
    • Morize, P.1    Baicry, J.2    Mardon, J.P.3
  • 12
    • 0006894206 scopus 로고
    • The Metallurgy of Zirconium
    • International Atomic Energy Agency, Vienna, Austria
    • Douglass, D. L., The Metallurgy of Zirconium, Atomic Energy Review, IAEA Supplement 1971, International Atomic Energy Agency, Vienna, Austria, 1971, p. 160.
    • (1971) Atomic Energy Review , Issue.IAEA SUPPL. 1971 , pp. 160
    • Douglass, D.L.1
  • 13
    • 49949122509 scopus 로고
    • Hydride Precipitates in Zirconium Alloys
    • Ells, C. E., "Hydride Precipitates in Zirconium Alloys," Journal of Nuclear Materials, Vol. 28, 1968, pp. 129-151.
    • (1968) Journal of Nuclear Materials , vol.28 , pp. 129-151
    • Ells, C.E.1
  • 14
    • 0022043251 scopus 로고
    • The Influence of Multiaxial States of Stress on Hydrogen Embrittlement of Zirconium Alloy Sheet
    • April
    • Yunchang, F. and Koss, D. A., "The Influence of Multiaxial States of Stress on Hydrogen Embrittlement of Zirconium Alloy Sheet," Metallurgical Transactions A, Vol. 16A, April 1985, pp. 675-681.
    • (1985) Metallurgical Transactions A , vol.16 A , pp. 675-681
    • Yunchang, F.1    Koss, D.A.2
  • 15
    • 5544249538 scopus 로고
    • Influence of Oxide Layer on the Hydride Embrittlement in Zircaloy-4
    • Bai, J. B., "Influence of Oxide Layer on the Hydride Embrittlement in Zircaloy-4," Scripta Metallurgica, 1993, pp. 617-622.
    • (1993) Scripta Metallurgica , pp. 617-622
    • Bai, J.B.1
  • 16
    • 51249167854 scopus 로고
    • Hydride Embrittlement in Zircaloy-4 Plate: Part I. Influence of Microstructure on the Hydride Embrittlement in Zircaloy-4 at 20°C and 350°C
    • June
    • Bai, J. B., Prioul, C. and Francois, D., "Hydride Embrittlement in Zircaloy-4 Plate: Part I. Influence of Microstructure on the Hydride Embrittlement in Zircaloy-4 at 20°C and 350°C," Metallurgical and Materials Transactions A, Vol. 25A, June 1994, pp. 1185-1197.
    • (1994) Metallurgical and Materials Transactions A , vol.25 A , pp. 1185-1197
    • Bai, J.B.1    Prioul, C.2    Francois, D.3
  • 18
    • 0345886684 scopus 로고
    • Combustion Engineering Report CEND-427, DOE/ET/34030-11, Department of Energy, Washington, DC, September
    • Garde, A. M., "Hot-Cell Examination of Extended Burnup Fuel from Fort Calhoun," Combustion Engineering Report CEND-427, DOE/ET/34030-11, Department of Energy, Washington, DC, September 1986.
    • (1986) Hot-Cell Examination of Extended Burnup Fuel from Fort Calhoun
    • Garde, A.M.1
  • 19
    • 5544221445 scopus 로고
    • Research Report EP80-16, Empire State Electric Energy Research Corporation, New York, Final Report, June
    • Nayak, U. P., Kunishi, H., and Smalley, W. R., "Hot-Cell Examination of Zion Fuel Cycle 5," Research Report EP80-16, Empire State Electric Energy Research Corporation, New York, Final Report, June 1985.
    • (1985) Hot-Cell Examination of Zion Fuel Cycle 5
    • Nayak, U.P.1    Kunishi, H.2    Smalley, W.R.3
  • 21
    • 0022562395 scopus 로고
    • Failure Strain for Irradiated Zircaloy Based on Subsized Specimen Testing and Analysis
    • W. R. Corwin and G. E. Lucas, Eds., American Society for Testing and Materials, West Conshohocken, PA
    • Adamson, R. B., Wisner, S. B., Tucker, R. P., and Rand, R. A., "Failure Strain for Irradiated Zircaloy Based on Subsized Specimen Testing and Analysis," Use of Small-Scale Specimens for Testing Irradiated Material, ASTM STP 888, W. R. Corwin and G. E. Lucas, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1986, pp. 171-185.
    • (1986) Use of Small-Scale Specimens for Testing Irradiated Material, ASTM STP 888 , pp. 171-185
    • Adamson, R.B.1    Wisner, S.B.2    Tucker, R.P.3    Rand, R.A.4
  • 22
    • 0020761487 scopus 로고
    • Inhomogeneous Plastic Deformation and Its Relevance to Iodine Stress Corrosion Cracking Susceptibility in Irradiated Zircaloy-2 Tubing
    • Onchi, T., Kayano, H., and Higaschiguchi, Y., "Inhomogeneous Plastic Deformation and Its Relevance to Iodine Stress Corrosion Cracking Susceptibility in Irradiated Zircaloy-2 Tubing," Journal of Nuclear Materials, Vol. 116, 1983, pp. 211-218.
    • (1983) Journal of Nuclear Materials , vol.116 , pp. 211-218
    • Onchi, T.1    Kayano, H.2    Higaschiguchi, Y.3
  • 23
    • 0020087331 scopus 로고
    • Evidence for Basal or Near-Basal Slip in Irradiated Zircaloy
    • Pettersson, K., "Evidence for Basal or Near-Basal Slip in Irradiated Zircaloy," Journal of Nuclear Materials, Vol. 105, 1982, pp. 341-344.
    • (1982) Journal of Nuclear Materials , vol.105 , pp. 341-344
    • Pettersson, K.1
  • 24
    • 0343689464 scopus 로고
    • Effects of Neutron Irradiation and Oxygen Content on the Microstructure and Mechanical Properties of Zircaloy
    • Proceedings of the International Symposium at X'ian, Republic of China, October Engineering Materials Advisory Services Ltd., Warley, United Kingdom
    • Adamson, R. B., and Bell, W. L. "Effects of Neutron Irradiation and Oxygen Content on the Microstructure and Mechanical Properties of Zircaloy," Microstructure and Mechanical Behavior of Materials, Vol. 1, Proceedings of the International Symposium at X'ian, Republic of China, October 1985, Engineering Materials Advisory Services Ltd., Warley, United Kingdom, pp. 237-246.
    • (1985) Microstructure and Mechanical Behavior of Materials , vol.1 , pp. 237-246
    • Adamson, R.B.1    Bell, W.L.2
  • 25
    • 0006998947 scopus 로고
    • Effects of Irradiation on the Microstructure of Zircaloy-4
    • A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, West Conshohocken, PA
    • Gilbon, D. and Simonot, C., "Effects of Irradiation on the Microstructure of Zircaloy-4," 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, West Conshohocken, PA, 1994, pp. 521-548.
    • (1994) Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245 , pp. 521-548
    • Gilbon, D.1    Simonot, C.2
  • 26
    • 0002542219 scopus 로고
    • Microstructural Aspects of Accelerated Deformation of Zircloy Nuclear Reactor Components during Service
    • presented at the 17th ASTM Symposium on Irradiation Effects on Materials, Sun Valley, Idaho, June 1994
    • Griffiths, M., Holt, R. A., and Rogerson, A., "Microstructural Aspects of Accelerated Deformation of Zircloy Nuclear Reactor Components During Service," presented at the 17th ASTM Symposium on Irradiation Effects on Materials, Sun Valley, Idaho, June 1994 Journal of Nuclear Materials, Vol. 225, 1995, pp. 245-258.
    • (1995) Journal of Nuclear Materials , vol.225 , pp. 245-258
    • Griffiths, M.1    Holt, R.A.2    Rogerson, A.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.