The Corrosion Properties of Zirconium-base Fuel Alloys PDF Download
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Author: Sam Kass
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 42
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Author: Sam Kass
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 42
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Book Description
Author: Stanley Kass
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 34
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Author: U.S. Atomic Energy Commission
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 252
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Author: L. F. Cochrun
Publisher:
ISBN:
Category : Reactor fuel reprocessing
Languages : en
Pages : 34
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Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1082
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Author: J. Paul Pemsler
Publisher:
ISBN:
Category : Steam
Languages : en
Pages : 26
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Author:
Publisher:
ISBN:
Category : Hafnium
Languages : en
Pages : 40
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Author: Gerry D. Moan
Publisher: ASTM International
ISBN: 0803128959
Category : Nuclear fuel claddings
Languages : en
Pages : 891
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Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.
Author: Helen C. Friedemann
Publisher:
ISBN:
Category : Uranium
Languages : en
Pages : 76
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Author:
Publisher:
ISBN:
Category : Energy development
Languages : en
Pages : 40
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