Author: Committee B-10 Staff
Publisher: ASTM International
ISBN:
Category : Uranium
Languages : en
Pages : 393
Book Description
Applications-Related Phenomena in Zirconium and Its Alloys
Author: Committee B-10 Staff
Publisher: ASTM International
ISBN:
Category : Uranium
Languages : en
Pages : 393
Book Description
Publisher: ASTM International
ISBN:
Category : Uranium
Languages : en
Pages : 393
Book Description
Scientific and Technical Aerospace Reports
Power Reactor Technology and Reactor Fuel Processing
Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 1110
Book Description
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 1110
Book Description
The Metallurgy of Zirconium
Author: David Leslie Douglass
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 496
Book Description
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 496
Book Description
Reactor Technology
Nuclear Science Abstracts
Reactor Technology
ASTM Special Technical Publication
Zirconium in the Nuclear Industry
Author: Gerry D. Moan
Publisher: ASTM International
ISBN: 0803128959
Category : Nuclear fuel claddings
Languages : en
Pages : 891
Book Description
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.
Publisher: ASTM International
ISBN: 0803128959
Category : Nuclear fuel claddings
Languages : en
Pages : 891
Book Description
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.