Zircaloy-4 Cladding Deformation During Power Reactor Irradiation PDF Download
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Author: DG. Franklin
Publisher:
ISBN:
Category : Cladding
Languages : en
Pages : 33
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Book Description
The four primary Zircaloy fuel cladding deformation phenomena--axial elongation, circumferential creep, ovalization, and ridging--have been investigated for fuel irradiated in four modern pressurized water reactors. The axial elongation of fueled and nonfueled rods is examined by a regression fit for dependence on fluence, clad texture, yield stress, applied stress and, for fuel rods, fuel pellet length to diameter ratio. For fueled rods, only fluence and stress are found to be important, although the range of texture data is small. For nonfueled rods, the texture is found to influence elongation.
Author: DG. Franklin
Publisher:
ISBN:
Category : Cladding
Languages : en
Pages : 33
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Book Description
The four primary Zircaloy fuel cladding deformation phenomena--axial elongation, circumferential creep, ovalization, and ridging--have been investigated for fuel irradiated in four modern pressurized water reactors. The axial elongation of fueled and nonfueled rods is examined by a regression fit for dependence on fluence, clad texture, yield stress, applied stress and, for fuel rods, fuel pellet length to diameter ratio. For fueled rods, only fluence and stress are found to be important, although the range of texture data is small. For nonfueled rods, the texture is found to influence elongation.
Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 308
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Book Description
Author: D. Franklin
Publisher: ASTM International
ISBN: 9780803107540
Category : Business & Economics
Languages : en
Pages : 516
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Book Description
Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 490
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Book Description
Author: CV. Dodd
Publisher:
ISBN:
Category : Creep properties
Languages : en
Pages : 20
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Book Description
Descriptions and results for seven of the eight in-reactor creepdown tests of Zircaloy fuel cladding, which were part of a joint program between the U.S. Nuclear Regulatory Commission and Energieonderzoek Centrum Nederland, are presented. These tests were conducted to study the behavior of Zircaloy fuel cladding under conditions that approximate those found in an operating pressurized-water power reactor.
Author: D. G. Franklin
Publisher: ASTM International
ISBN: 9780803102590
Category : Science
Languages : en
Pages : 322
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Book Description
Author: George P. Sabol
Publisher: ASTM International
ISBN: 0803124066
Category : Nuclear fuel claddings
Languages : en
Pages : 907
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Book Description
Author: D.K. Jha
Publisher: Discovery Publishing House
ISBN: 9788171418831
Category :
Languages : en
Pages : 230
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Book Description
This book elements of nuclear reactors has been written to meet the requirement of the student of pass course, honours and post graduate students the subject matter of this book is presented in very straightforward matter. Nuclear reactors is a very important part of nuclear physics, having a broad field, we have try to maintain this field under the small volume according our best adherence. Contents: Interactions of Nuclear Radiation with Matter, Nuclear Reactions, Nuclear Models, Neutrons.
Author: J. O. Barner
Publisher:
ISBN:
Category : Nuclear fuel claddings
Languages : en
Pages : 124
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Book Description
Author: DL. Baty
Publisher:
ISBN:
Category : Alloys
Languages : en
Pages : 34
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Book Description
Thermomechanical processing of Zircaloy-4 cladding plays a major role in determining its deformation behavior. Crystallographic texture and the related anisotropy in mechanical properties of Zircaloy-4 have been shown to be affected by different processing paths. In this program, the deformation behavior of four Zircaloy-4 cladding types was evaluated in laboratory and in-reactor studies under typical pressurized-water reactor (PWR) conditions. In particular, the creep behavior, stress-free growth, and mechanical property changes of these materials were examined.
