Anisotropy of irradiation Creep and growth of zirconium alloy pressure tubes

Anisotropy of irradiation Creep and growth of zirconium alloy pressure tubes PDF Author: R. A. Holt
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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Anisotropy of irradiation Creep and growth of zirconium alloy pressure tubes

Anisotropy of irradiation Creep and growth of zirconium alloy pressure tubes PDF Author: R. A. Holt
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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Creep of Zirconium Alloys in Nuclear Reactors

Creep of Zirconium Alloys in Nuclear Reactors PDF Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 308

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Creep of Zirconium Alloys in Nuclear Reactors

Creep of Zirconium Alloys in Nuclear Reactors PDF Author: D. G. Franklin
Publisher: ASTM International
ISBN: 9780803102590
Category : Science
Languages : en
Pages : 322

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Factors Affecting the Anisotropy of Irradiation Creep and Growth of Zirconium Alloys

Factors Affecting the Anisotropy of Irradiation Creep and Growth of Zirconium Alloys PDF Author: Holt, R. A
Publisher: [London] : Pergamon Press
ISBN:
Category :
Languages : en
Pages : 10

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In-Reactor Deformation of Zirconium Alloy Components

In-Reactor Deformation of Zirconium Alloy Components PDF Author: R. A. Holt
Publisher:
ISBN:
Category : Anisotropy
Languages : en
Pages : 16

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This paper briefly reviews work by the author identifying and describing in-reactor deformation mechanisms of materials and structures used in nuclear reactors, in particular, Zircaloy-2, Zircaloy-4, and Zr-2.5Nb, and the CANDU fuel channel (comprising Zr alloy pressure tubes, calandria tubes, and spacers). The discussion is set in the context of contemporary findings of other workers in the international community. The following themes are highlighted: The contributions of creep and growth to deformation; c-component dislocations and the fluence dependence of irradiation growth; anisotropy of irradiation growth; deformation equations and pressure tube-to-calandria tube contact in CANDU reactors; low temperature flux (damage rate) dependence of deformation rates. The first developments were reported in 1976 at the third conference in this series and there are ongoing developments in all areas. The linear low temperature flux dependence of creep and growth rates is yet to be satisfactorily explained.

Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry PDF Author: ASTM Committee B-10 on Reactive and Refractory Metals and Alloys
Publisher: ASTM International
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 694

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Effects of Anisotropy and Irradiation on the Creep Behavior of Zircaloy-2

Effects of Anisotropy and Irradiation on the Creep Behavior of Zircaloy-2 PDF Author: Glenn E. Lucas
Publisher: Dissertations-G
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 394

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The Effects of Microstructure and Operating Conditions on Irradiation Creep of Zr-2.5Nb Pressure Tubing

The Effects of Microstructure and Operating Conditions on Irradiation Creep of Zr-2.5Nb Pressure Tubing PDF Author: L. Walters
Publisher:
ISBN:
Category : In-reactor deformation
Languages : en
Pages : 33

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Creep experiments have been performed on biaxially stressed 10 mm diameter Zr-2.5Nb capsules. As the pressurized capsules were obtained from micro-pressure tubes, which were fabricated by the same process as CANDU power reactor pressure tubes, they have a similar microstructure to that of the full-size tubes. The experiments were performed in the OSIRIS test reactor at nominal operating temperatures ranging from 553 and 613 K in fast neutron fluxes up to 2 x 1018 n.m-2.s-1 (E > 1 MeV). Diametral and axial strains are reported as functions of fluence for specimens internally pressurized to hoop stresses from 0 to 160 MPa and irradiated to 26.5 dpa. The effects of microstructure, temperature, and cold work on irradiation creep are shown. The analysis of OSIRIS data combined with data from in-service CANDU tubes has revealed some significant observations regarding pressure tube deformation: (i) that irradiation creep anisotropy varies with temperature, (ii) texture appears to have a more significant effect on axial creep than on diametral creep, (iii) diametral strain appears to be strongly dependent on grain size and aspect ratio, and (iv) that whereas cold-work correlates with the axial creep of the capsules, there appears to be no statistically significant dependence of diametral creep on cold-work.

Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry PDF Author: R. B. Adamson
Publisher: ASTM International
ISBN: 0803109350
Category : Creep
Languages : en
Pages : 832

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In-Reactor Creep of Zr-2.5Nb

In-Reactor Creep of Zr-2.5Nb PDF 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.