Zirconium in the Nuclear Industry PDF Download
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Author: Leo F. P. Van Swam
Publisher: ASTM International
ISBN: 0803111991
Category : Nuclear fuel claddings
Languages : en
Pages : 781
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Book Description
Author: Leo F. P. Van Swam
Publisher: ASTM International
ISBN: 0803111991
Category : Nuclear fuel claddings
Languages : en
Pages : 781
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Book Description
Author: Spencer H. Bush
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 128
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Book Description
Author: M. Kangilaski
Publisher:
ISBN:
Category : Metals
Languages : en
Pages : 264
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Book Description
Author: Gerry D. Moan
Publisher: ASTM International
ISBN: 0803128959
Category : Nuclear fuel claddings
Languages : en
Pages : 891
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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.
Author: George P. Sabol
Publisher: ASTM International
ISBN: 0803124066
Category : Nuclear fuel claddings
Languages : en
Pages : 907
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Book Description
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 764
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Book Description
Author: A. L. Bement
Publisher: ASTM International
ISBN: 9780803100695
Category : Neutron flux
Languages : en
Pages : 571
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Book Description
Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 1338
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Book Description
Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 466
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Book Description
Author: Frederic R. Shober
Publisher:
ISBN:
Category : Metals
Languages : en
Pages : 120
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Book Description
The effect of fast-neutron (>1 Mev) irradiation on the mechanical properties of structural metals and alloys was studied. Although the yield strengths and ultimate tensile strengths are increased su stantially for most materials, the ductility suffers severe decreases. This report presents these changes in properties of several structural metals for a number of neutron exposures within the 1.0 x 10 to the 18th power to 5.0 x 10 to the 21st power n/sq cm range. Data summarizing these effects on several classes of materials such as carbon steels, low-alloy steels, stainless steels, Zr-base alloys, ni-base alloys, Al-base alloys, and Ta are given. Additional data which show the influence f irradiation temperatures and of post-irradiation annealing on the radiation-induced property changes are also given and discussed. Increases as great as 175% in yield strength, 100% in ultimate strength, and decreases of 80% in total elongation are reported for fast-neutron exposures as great as 5 10 to the 21st power n/sq cm. (Author).
