Creep of Zirconium Alloys in Nuclear Reactors PDF Download
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Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 308
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Book Description
Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 308
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Book Description
Author: D. G. Franklin
Publisher: ASTM International
ISBN: 9780803102590
Category : Science
Languages : en
Pages : 322
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Book Description
Author: AR. Causey
Publisher:
ISBN:
Category : Alloys
Languages : en
Pages : 20
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Book Description
The anisotropy of irradiation creep of Zr-2.5Nb alloy tubes at 570 K has been investigated using creep of helical springs and stress relaxation of twisted rods and bent beams. These tests measure creep rate directly since strains associated with irradiation growth are absent. Creep rates from these tests and from results on creep of pressurized tubes reported in the literature can be correlated through consideration of the crystallographic texture, slip systems, and dislocation density of the Zr-2.5Nb tubing. A creep model based on glide of 1/311 ̄20 type dislocations on prismatic planes in combination with secondary glide of 1/311 ̄22 dislocations on {10 ̄11} pyramidal planes provides a consistent correlation. The creep rate is only slightly dependent on dislocation density as measured by X-ray diffraction.
Author: A. R. Causey
Publisher: Chalk River, Ont. : Reactor Materials Research Branch, Chalk River Laboratories
ISBN: 9780660155210
Category : Nuclear reactors
Languages : en
Pages : 22
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Book Description
Author: V. Fidleris
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
Author: V. Fidleris
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
Author: V. Fidleris
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
Author: P. A. Ross-Ross
Publisher:
ISBN:
Category :
Languages : en
Pages : 36
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Book Description
Author: V. Fidleris
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Book Description
Author: EF. Ibrahim
Publisher:
ISBN:
Category : Cold working
Languages : en
Pages : 14
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Book Description
Tubular specimens of Zr-2.5Nb, 23 mm internal diameter, have been creep tested in-reactor at 570 K. Specimens were biaxially stressed by internal pressure, with transverse stresses from 103 to 317 MPa. Two separate experiments are reported (a) U-501/2 which has specimens quenched from 1045 K; cold drawn 2, 12, or 20 percent and aged at 773 K for 24 h, and (b) U-501/3 which has specimens extruded; cold drawn 10, 23, or 33 percent and stress relieved at 673 K for 12 h.
