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84920632865
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Effect of Chemistry on Elevated Temperature Nodular Corrosion
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American Society for Testing and Materials, West Conshohocken, PA
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Weidinger, H. G., Garzarolli, F., Eucken, C. M., and Baroch, E. F., "Effect of Chemistry on Elevated Temperature Nodular Corrosion," Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939, American Society for Testing and Materials, West Conshohocken, PA, 1987, pp. 364-386.
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Weidinger, H.G.1
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2
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0343689478
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Influence of Chemical Composition on Uniform Corrosion of Zirconium Base Alloys in Autoclave Tests
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American Society for Testing and Materials, West Conshohocken, PA
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Eucken, C. M., Finden, P. T., Trapp-Pritsching, S., and Weidinger, H. G., "Influence of Chemical Composition on Uniform Corrosion of Zirconium Base Alloys in Autoclave Tests," Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023, American Society for Testing and Materials, West Conshohocken, PA, 1989, pp. 113-127.
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Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023
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Eucken, C.M.1
Finden, P.T.2
Trapp-Pritsching, S.3
Weidinger, H.G.4
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3
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0009949198
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Progress in the Knowledge of Nodular Corrosion
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American Society for Testing and Materials, West Conshohocken, PA
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Garzarolli, F., Stehle, H., Steinberg, E., and Weidinger, H. G., "Progress in the Knowledge of Nodular Corrosion," Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939, American Society for Testing and Materials, West Conshohocken, PA, 1987, pp. 364-386.
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Zirconium in the Nuclear Industry: Seventh International Symposium, ASTM STP 939
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Garzarolli, F.1
Stehle, H.2
Steinberg, E.3
Weidinger, H.G.4
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4
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0342385305
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Microstructure and Corrosion Studies for Optimized PWR and BWR Zircaloy Cladding
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American Society for Testing and Materials, West Conshohocken, PA
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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, American Society for Testing and Materials, West Conshohocken, PA, 1989, p. 202.
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Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023
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Garzarolli, F.1
Steinberg, E.2
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0342385212
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Cladding and Structural Material Development for the Advanced Siemens PWR Fuel FOCUS
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Proceedings, Avignon, France
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Fuchs, H. P. et al., "Cladding and Structural Material Development for the Advanced Siemens PWR Fuel FOCUS," Proceedings, ANS-ENS Internal Topical Meeting on LWR Fuel Performance, Avignon, France, 1991, p. 682.
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Fuchs, H.P.1
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6
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0040703587
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Corrosion Optimized Zircaloy for BWR Fuel Elements
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American Society for Testing and Materials, West Conshohocken, PA
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Garzarolli, F., Schumann, R., and Steinberg, E., "Corrosion Optimized Zircaloy for BWR Fuel Elements," Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245, American Society for Testing and Materials, West Conshohocken, PA, 1994, p. 709.
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Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245
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Garzarolli, F.1
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Steinberg, E.3
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7
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5544317751
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Progress m Understanding PWR Fuel Rod Waterside Corrosion
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Proceedings, Orlando
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Garzarolli, F., Bodmer, R. P., Stehle, H., and Trapp-Pritsching, S., "Progress m Understanding PWR Fuel Rod Waterside Corrosion," Proceedings, ANS Topical Meeting on LWR Fuel Performance, Orlando, Vol. I, 1985, pp. 3-55.
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ANS Topical Meeting on LWR Fuel Performance
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Garzarolli, F.1
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Trapp-Pritsching, S.4
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0343254731
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Corrosion Performance of Some Zirconium Alloys Irradiated in the Steam Generating Heavy Water Reactor Winfrith
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Proceedings, Myrtle Beach, SC, NACE
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Cheng, B. et al.. "Corrosion Performance of Some Zirconium Alloys Irradiated in the Steam Generating Heavy Water Reactor Winfrith," Proceedings, International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Myrtle Beach, SC, 1983, NACE, p 274
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Cheng, B.1
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5544326592
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In BWR and Out-of-Pile Nodular Corrosion Behavior of Zry 2/4 Type Melts with Varying Fe, Cr, and Ni Contents and Varying Process History
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Proceedings, 11-14 Sept.
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Ruhman, H., Manzel, R., and Charquet, D., "In BWR and Out-of-Pile Nodular Corrosion Behavior of Zry 2/4 Type Melts with Varying Fe, Cr, and Ni Contents and Varying Process History," Proceedings Eleventh ASTM Symposium on Zirconium in the Nuclear Industry, 11-14 Sept. 1995.
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(1995)
Eleventh ASTM Symposium on Zirconium in the Nuclear Industry
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Ruhman, H.1
Manzel, R.2
Charquet, D.3
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0342820027
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Optimized Zry-4 with Enhanced Fe and Cr Content and DUPLEX Cladding: The Answer to Corrosion on PWR
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Proceedings, TOPFUEL 95, Würzburg, Germany, 12-15 March
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Seibold, A., Garzarolli, F., and Steinberg, E., "Optimized Zry-4 with Enhanced Fe and Cr Content and DUPLEX Cladding: the Answer to Corrosion on PWR," Proceedings, International KTG/ENS Topical Meeting on Nuclear Fuel, TOPFUEL 95, Würzburg, Germany, 12-15 March 1995, Vol. II, p. 117.
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(1995)
International KTG/ENS Topical Meeting on Nuclear Fuel
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Seibold, A.1
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