Corrosion and Failure Characteristics of Zirconium Alloys in High-Pressure Steam in the Temperature Range 400 to 500 C
Language: en
Pages: 15
Authors: A. B. Johnson
Categories: Catastrophic corrosion
Type: BOOK - Published: 1969 - Publisher:

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A nuclear fuel-failure phenomenon prompted a study of the corrosion properties of the Zircaloy-2 fuel cladding. The principal studies were conducted at 400, 450
Zirconium in the Nuclear Industry
Language: en
Pages: 832
Authors: R. B. Adamson
Categories: Creep
Type: BOOK - Published: 1987 - Publisher: ASTM International

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Zirconium in the Nuclear Industry
Language: en
Pages: 794
Authors: Craig M. Eucken
Categories: Nuclear fuel claddings
Type: BOOK - Published: 1991 - Publisher: ASTM International

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The proceedings of the Ninth International Symposium on [title], held in Kobe, Japan, November 1990, address current trends in the development, performance, and
Applications-Related Phenomena in Zirconium and Its Alloys
Language: en
Pages: 393
Authors: Committee B-10 Staff
Categories: Uranium
Type: BOOK - Published: 1969 - Publisher: ASTM International

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