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1
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0342820015
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Improvements in Zirconium Alloy Corrosion Resistance
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International Atomic Energy Agency, Vienna, IWGFPT/34
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Kilp, G. R. Thornburg, D. R., and Comstock, R. J., "Improvements in Zirconium Alloy Corrosion Resistance," Proceedings, IAEA Technical Committee Meeting on Fundamental Aspects of Corrosion on Zirconium Base Alloys in Water Reactor Environments, International Atomic Energy Agency, Vienna, IWGFPT/34, 1990, pp. 145-157.
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Proceedings, IAEA Technical Committee Meeting on Fundamental Aspects of Corrosion on Zirconium Base Alloys in Water Reactor Environments
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Kilp, G.R.1
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Comstock, R.J.3
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2
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0342385305
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Microstructure and Corrosion Studies for Optimized PWR and BWR Zircaloy Cladding
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L. F. P. Van Swam and C. M. Euken, Eds., American Society for Testing and Materials, Philadelphia
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Garzarolli, F., Steinberg, E., and Weidinger, H. G., "Microstructure and Corrosion Studies for Optimized PWR and BWR Zircaloy Cladding," Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023, L. F. P. Van Swam and C. M. Euken, Eds., American Society for Testing and Materials, Philadelphia, 1989, pp. 202-212.
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(1989)
Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023
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Garzarolli, F.1
Steinberg, E.2
Weidinger, H.G.3
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3
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84947823849
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Mechanistic Studies of Zircaloy Nodular Corrosion
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R. B. Adamson and L. F. P. Van Swam, Eds., American Society for Testing and Materials, Philadelphia
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Cheng, B. and Adamson, R. B., "Mechanistic Studies of Zircaloy Nodular Corrosion," 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, Philadelphia, 1987, pp. 387-416.
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(1987)
Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939
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Cheng, B.1
Adamson, R.B.2
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4
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84915870653
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Influence of Variations in Early Fabrication Steps on Corrosion, Mechanical Properties, and Structure of Zircaloy-4 Products
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R. B. Adamson and L. F. P. Van Swam, Eds., American Society for Testing and Materials, Philadelphia
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Charquet, D., Steinberg, E., and Millet, Y., "Influence of Variations in Early Fabrication Steps on Corrosion, Mechanical Properties, and Structure of Zircaloy-4 Products," 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, Philadelphia, 1987, pp. 432-447.
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(1987)
Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939
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Charquet, D.1
Steinberg, E.2
Millet, Y.3
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5
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0342385205
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Corrosion Behavior of Zircaloy-4 Cladding with Varying Tin Content in High-Temperature Pressurized Water Reactors
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A. M. Garde and E. R. Bradley, Eds., American Society for Testing and Materials, Philadelphia
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Garde, A. M., Pati, S. R., Krammen, M. A., Smith G. P., and Endter, R. K., "Corrosion Behavior of Zircaloy-4 Cladding with Varying Tin Content in High-Temperature Pressurized Water Reactors," 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, 1994, pp. 760-778.
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(1994)
Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245
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Garde, A.M.1
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Krammen, M.A.3
Smith, G.P.4
Endter, R.K.5
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6
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0021633101
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Analytical Approaches and Experimental Verification to Describe the Influence of Cold Work and Heat Treatment on the Mechanical Properties of Zircaloy Cladding Tubes
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D. G. Franklin and R. B. Adamson, Eds., American Society for Testing and Materials, Philadelphia
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Steinberg, E., Weidinger, H. G., and Schaa, A., "Analytical Approaches and Experimental Verification to Describe the Influence of Cold Work and Heat Treatment on the Mechanical Properties of Zircaloy Cladding Tubes," Zirconium in the Nuclear Industry: Sixth International Symposium, ASTM STP 824, D. G. Franklin and R. B. Adamson, Eds., American Society for Testing and Materials, Philadelphia, 1984, pp. 106-122.
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(1984)
Zirconium in the Nuclear Industry: Sixth International Symposium, ASTM STP 824
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Steinberg, E.1
Weidinger, H.G.2
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7
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0342385295
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Influence of Thermal Processing and Microstructure on the Corrosion Behavior of Zircaloy-4 Tubing
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International Atomic Energy Agency, Vienna, IAEA-SM-288/59
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Anderson, T., Thorvaldsson, T., Wilson, A., and Wardle, A. M., "Influence of Thermal Processing and Microstructure on the Corrosion Behavior of Zircaloy-4 Tubing," Proceedings, IAEA Symposium on Improvements in Water Reactor Fuel Technology and Utilization, International Atomic Energy Agency, Vienna, IAEA-SM-288/59, 1987, pp. 435-449.
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(1987)
Proceedings, IAEA Symposium on Improvements in Water Reactor Fuel Technology and Utilization
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Anderson, T.1
Thorvaldsson, T.2
Wilson, A.3
Wardle, A.M.4
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8
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5544282061
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Behavior of Structural Materials for Fuel and Control Elements in Light Water Cooled Power Reactors
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International Atomic Energy Agency, Vienna, IAEA-SM-288/24
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Garzarolli, F. and Stehle, H., "Behavior of Structural Materials for Fuel and Control Elements in Light Water Cooled Power Reactors," Proceedings, IAEA Symposium on Improvements in Water Reactor Fuel Technology and Utilization, International Atomic Energy Agency, Vienna, IAEA-SM-288/24, 1987, pp. 387-407.
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(1987)
Proceedings, IAEA Symposium on Improvements in Water Reactor Fuel Technology and Utilization
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Garzarolli, F.1
Stehle, H.2
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9
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85170074851
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The Corrosion Behavior of 2.5Nb Zirconium Alloy
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American Society for Testing and Materials, Philadelphia
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LeSurf, J. E., "The Corrosion Behavior of 2.5Nb Zirconium Alloy," Applications-Related Phenomena for Zirconium and Its Alloys, ASTM STP 458, American Society for Testing and Materials, Philadelphia, 1969, pp. 286-300.
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(1969)
Applications-Related Phenomena for Zirconium and Its Alloys, ASTM STP 458
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LeSurf, J.E.1
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10
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84898021248
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Effects of Nuclear Radiation on the Corrosion, Hydriding, and Oxide Properties of Six Zirconium Alloys
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American Society for Testing and Materials Philadelphia
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Johnson, A. B., Jr., "Effects of Nuclear Radiation on the Corrosion, Hydriding, and Oxide Properties of Six Zirconium Alloys," Applications-Related Phenomena for Zirconium and Its Alloys, ASTM STP 458, American Society for Testing and Materials Philadelphia, 1969, pp. 301-324.
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(1969)
Applications-Related Phenomena for Zirconium and Its Alloys, ASTM STP 458
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Johnson A.B., Jr.1
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11
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0016435964
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Effect of Ageing and Irradiation on the Corrosion of Zr-2.5 Wt%NB
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Urbanic, V. F., LeSurf, J. E., and Johnson, A. B., Jr., "Effect of Ageing and Irradiation on the Corrosion of Zr-2.5 Wt%NB," Corrosion, Vol. 31, 1975, p. 15.
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0040527137
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Improved PWR Fuel Cladding
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International Atomic Energy Agency, Vienna, IAEA-TECDOC-665
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Sabol, G. P., Schoenberger, G., and Balfour, M. G., "Improved PWR Fuel Cladding," Proceedings, IAEA Technical Committee Meeting on Materials for Advanced Water Cooled Reactors, International Atomic Energy Agency, Vienna, IAEA-TECDOC-665, 1992, pp. 122-130.
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Sabol, G.P.1
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13
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0014743786
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Precipitation Behavior in Zr-2.5 Wt%Nb Alloy
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Sabol, G. P., "Precipitation Behavior in Zr-2.5 Wt%Nb Alloy," Journal of Nuclear Materials, Vol. 34, 1970, p. 142.
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Sabol, G.P.1
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0026399208
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Effect of Alloying Elements on Uniform Corrosion Resistance of Zirconium-Based Alloys in 360°C Water and 400°C Steam
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C. M. Eucken and A. M. Garde, Eds., American Society for Testing and Materials, Philadelphia
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Harada, M., Kimpara, M., and Abe, K., "Effect of Alloying Elements on Uniform Corrosion Resistance of Zirconium-Based Alloys in 360°C Water and 400°C Steam," Zirconium in the Nuclear Industry: Ninth International Symposium, ASTM STP 1132, C. M. Eucken and A. M. Garde, Eds., American Society for Testing and Materials, Philadelphia, 1991, pp. 368-391.
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(1991)
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Harada, M.1
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