Author: J. W. Weber
Publisher:
ISBN:
Category :
Languages : en
Pages : 58
Book Description
Final Report
Author: J. W. Weber
Publisher:
ISBN:
Category :
Languages : en
Pages : 58
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 58
Book Description
Interdiffusion in Zircaloy-2 Clad U-2 W/o Zr Fuel Materials and Its Effect Upon Corrosion Behavior
Author: A. L. Geary
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 28
Book Description
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 28
Book Description
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.
Development and Properties of Coextruded Zircaloy-clad Uranium Fuel Elements with Integral End Seals
Author: H. F. Sawyer
Publisher:
ISBN:
Category : Extrusion process
Languages : en
Pages : 82
Book Description
Publisher:
ISBN:
Category : Extrusion process
Languages : en
Pages : 82
Book Description
Proceedings of the USAEC Symposium on Zirconium Alloy Development, Castlewood, Pleasanton, California, November 12-14, 1962
Author:
Publisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 422
Book Description
Publisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 422
Book Description
Oxide Particle Size Distribution from Shearing Irradiated and Unirradiated LWR Fuels in Zircaloy and Stainless Steel Cladding
Author: Wallace Davis
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 52
Book Description
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 52
Book Description
Internal Zirconium Hydride Formation in Zircaloy Fuel Element Cladding Under Irradiation
Author: J. M. Markowitz
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 52
Book Description
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 52
Book Description
Zirconium in the Nuclear Industry
Author: Bruce Kammenzind
Publisher:
ISBN: 9780803145146
Category : Electronic book
Languages : en
Pages : 821
Book Description
"The latest in this popular series provides 44 peer-reviewed papers on the latest international research covering all aspects of zirconium alloy properties and performance relevant to the nuclear industry. Topics address: All aspects of the fuel cycle ; Basic metallurgy ; Spent fuel ; Corrosion ; Mechanical properties ; Deformations mechanisms ; Failure mechanisms ; LOCA and Transients. These papers provide examples of studies where experimental techniques are combined with analytical tools and calculations; reflect a stronger trend towards efforts that enable fundamental in-reactor measurements, which are essential for further development of experimental techniques as well as for the possibility to enhance the development of improved alloys; and examine an increasing number of alternative alloys being developed and verified."--Publisher's website.
Publisher:
ISBN: 9780803145146
Category : Electronic book
Languages : en
Pages : 821
Book Description
"The latest in this popular series provides 44 peer-reviewed papers on the latest international research covering all aspects of zirconium alloy properties and performance relevant to the nuclear industry. Topics address: All aspects of the fuel cycle ; Basic metallurgy ; Spent fuel ; Corrosion ; Mechanical properties ; Deformations mechanisms ; Failure mechanisms ; LOCA and Transients. These papers provide examples of studies where experimental techniques are combined with analytical tools and calculations; reflect a stronger trend towards efforts that enable fundamental in-reactor measurements, which are essential for further development of experimental techniques as well as for the possibility to enhance the development of improved alloys; and examine an increasing number of alternative alloys being developed and verified."--Publisher's website.
Zirconium in the Nuclear Industry: Proceedings of the Third International Conference
Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 681
Book Description
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 681
Book Description
Zirconium in the Nuclear Industry
Author: R. B. Adamson
Publisher: ASTM International
ISBN: 0803109350
Category : Creep
Languages : en
Pages : 832
Book Description
Publisher: ASTM International
ISBN: 0803109350
Category : Creep
Languages : en
Pages : 832
Book Description