The Effect of Neutron Irradiation and Cold Work on the Strain-Aging Behavior of Zircaloy-2 PDF Download
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Author: W. B. Rotsey
Publisher:
ISBN:
Category : Cold working
Languages : en
Pages : 16
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Book Description
The strain-aging behavior of annealed Zircaloy-2 in vacuum was studied as a function of deformation temperature, integrated fast-neutron dose, and degree of cold work. Strain aging occurred in the temperature range 200 to 500 C. Transmission electron microscopy showed that in the temperature range 300 to 450 C, dislocations were arranged in a cell structure, and that at 500 C two-dimensional hexagonal dislocation nets were present. Between 200 and 400 C, the strain aging was found to be due to the presence of oxygen; however, the origin of the strain aging between 400 and 500 C was not identified.
Author: W. B. Rotsey
Publisher:
ISBN:
Category : Cold working
Languages : en
Pages : 16
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Book Description
The strain-aging behavior of annealed Zircaloy-2 in vacuum was studied as a function of deformation temperature, integrated fast-neutron dose, and degree of cold work. Strain aging occurred in the temperature range 200 to 500 C. Transmission electron microscopy showed that in the temperature range 300 to 450 C, dislocations were arranged in a cell structure, and that at 500 C two-dimensional hexagonal dislocation nets were present. Between 200 and 400 C, the strain aging was found to be due to the presence of oxygen; however, the origin of the strain aging between 400 and 500 C was not identified.
Author: Committee B-10 Staff
Publisher: ASTM International
ISBN:
Category : Uranium
Languages : en
Pages : 393
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Author: Arden Lee Bement (Jr.)
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 214
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Author: A. L. Bement
Publisher:
ISBN:
Category : Zirconium-tin alloys
Languages : en
Pages : 416
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Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 850
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Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 68
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Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 308
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Author: Craig M. Eucken
Publisher: ASTM International
ISBN: 080311463X
Category : Nuclear fuel claddings
Languages : en
Pages : 794
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Book Description
The proceedings of the Ninth International Symposium on [title], held in Kobe, Japan, November 1990, address current trends in the development, performance, and fabrication of zirconium alloys for nuclear power reactors. the bulk of the most recent work on zirconium alloy behavior has concerned corr
Author: D. G. Franklin
Publisher: ASTM International
ISBN: 9780803102590
Category : Science
Languages : en
Pages : 322
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Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 448
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