Author: R. W. L. Fong
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
The possibility of accelerating creep at low temperature in annealed zircaloy at high fluences, similar to previously reported growth 'breakaway' behaviour at temperatures above 500 k, has been investigated at 340 k using stress relaxation and irradiation growth tests on annealed zircaloy-4 pre-irradiated at 580 k to 5 x 10sup(24) and 8 x 10sup(25) n.m-2 e1 mev. test results suggest that both creep and growth rates are higher for the specimens pre-irradiated to the higher fluence, however, the stress relaxation data are not conclusive. the presence of c component dislocations, revealed by transmission electron microscopy, only in the high fluence material has been related previously to the growth 'breakaway' at 580 k, and appears to result in higher growth and creep rates at 340 k.
Investigation of zirconium hydrides and hydrogen solubility limit in zr-2.5 nb alloy by small angle neutron scattering
Author: R. W. L. Fong
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
The possibility of accelerating creep at low temperature in annealed zircaloy at high fluences, similar to previously reported growth 'breakaway' behaviour at temperatures above 500 k, has been investigated at 340 k using stress relaxation and irradiation growth tests on annealed zircaloy-4 pre-irradiated at 580 k to 5 x 10sup(24) and 8 x 10sup(25) n.m-2 e1 mev. test results suggest that both creep and growth rates are higher for the specimens pre-irradiated to the higher fluence, however, the stress relaxation data are not conclusive. the presence of c component dislocations, revealed by transmission electron microscopy, only in the high fluence material has been related previously to the growth 'breakaway' at 580 k, and appears to result in higher growth and creep rates at 340 k.
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
The possibility of accelerating creep at low temperature in annealed zircaloy at high fluences, similar to previously reported growth 'breakaway' behaviour at temperatures above 500 k, has been investigated at 340 k using stress relaxation and irradiation growth tests on annealed zircaloy-4 pre-irradiated at 580 k to 5 x 10sup(24) and 8 x 10sup(25) n.m-2 e1 mev. test results suggest that both creep and growth rates are higher for the specimens pre-irradiated to the higher fluence, however, the stress relaxation data are not conclusive. the presence of c component dislocations, revealed by transmission electron microscopy, only in the high fluence material has been related previously to the growth 'breakaway' at 580 k, and appears to result in higher growth and creep rates at 340 k.
Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
Author: John H. Jackson
Publisher: Springer
ISBN: 3030046397
Category : Technology & Engineering
Languages : en
Pages : 2532
Book Description
This two-volume set represents a collection of papers presented at the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The purpose of this conference series is to foster an exchange of ideas about problems and their remedies in water-cooled nuclear power plants of today and the future. Contributions cover problems facing nickel-based alloys, stainless steels, pressure vessel and piping steels, zirconium alloys, and other alloys in water environments of relevance. Components covered include pressure boundary components, reactor vessels and internals, steam generators, fuel cladding, irradiated components, fuel storage containers, and balance of plant components and systems.
Publisher: Springer
ISBN: 3030046397
Category : Technology & Engineering
Languages : en
Pages : 2532
Book Description
This two-volume set represents a collection of papers presented at the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The purpose of this conference series is to foster an exchange of ideas about problems and their remedies in water-cooled nuclear power plants of today and the future. Contributions cover problems facing nickel-based alloys, stainless steels, pressure vessel and piping steels, zirconium alloys, and other alloys in water environments of relevance. Components covered include pressure boundary components, reactor vessels and internals, steam generators, fuel cladding, irradiated components, fuel storage containers, and balance of plant components and systems.
The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components
Author: Manfred P. Puls
Publisher: Springer Science & Business Media
ISBN: 1447141954
Category : Science
Languages : en
Pages : 475
Book Description
By drawing together the current theoretical and experimental understanding of the phenomena of delayed hydride cracking (DHC) in zirconium alloys, The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components: Delayed Hydride Cracking provides a detailed explanation focusing on the properties of hydrogen and hydrides in these alloys. Whilst the emphasis lies on zirconium alloys, the combination of both the empirical and mechanistic approaches creates a solid understanding that can also be applied to other hydride forming metals. This up-to-date reference focuses on documented research surrounding DHC, including current methodologies for design and assessment of the results of periodic in-service inspections of pressure tubes in nuclear reactors. Emphasis is placed on showing how our understanding of DHC is supported by progress in general understanding of such broad fields as the study of hysteresis associated with first order phase transformations, phase relationships in coherent crystalline metallic solids, the physics of point and line defects, diffusion of substitutional and interstitial atoms in crystalline solids, and continuum fracture and solid mechanics. Furthermore, an account of current methodologies is given illustrating how such understanding of hydrogen, hydrides and DHC in zirconium alloys underpins these methodologies for assessments of real life cases in the Canadian nuclear industry. The all-encompassing approach makes The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Component: Delayed Hydride Cracking an ideal reference source for students, researchers and industry professionals alike.
Publisher: Springer Science & Business Media
ISBN: 1447141954
Category : Science
Languages : en
Pages : 475
Book Description
By drawing together the current theoretical and experimental understanding of the phenomena of delayed hydride cracking (DHC) in zirconium alloys, The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components: Delayed Hydride Cracking provides a detailed explanation focusing on the properties of hydrogen and hydrides in these alloys. Whilst the emphasis lies on zirconium alloys, the combination of both the empirical and mechanistic approaches creates a solid understanding that can also be applied to other hydride forming metals. This up-to-date reference focuses on documented research surrounding DHC, including current methodologies for design and assessment of the results of periodic in-service inspections of pressure tubes in nuclear reactors. Emphasis is placed on showing how our understanding of DHC is supported by progress in general understanding of such broad fields as the study of hysteresis associated with first order phase transformations, phase relationships in coherent crystalline metallic solids, the physics of point and line defects, diffusion of substitutional and interstitial atoms in crystalline solids, and continuum fracture and solid mechanics. Furthermore, an account of current methodologies is given illustrating how such understanding of hydrogen, hydrides and DHC in zirconium alloys underpins these methodologies for assessments of real life cases in the Canadian nuclear industry. The all-encompassing approach makes The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Component: Delayed Hydride Cracking an ideal reference source for students, researchers and industry professionals alike.
Proceedings of the USAEC Symposium on Zirconium Alloy Development, Castlewood, Pleasanton, California, November 12-14, 1962
Author:
Publisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 422
Book Description
Publisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 422
Book Description
Metals Abstracts
Author:
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 1042
Book Description
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 1042
Book Description
Study of the Nickel-zirconium-hydrogen System
Author: I. R. Tannenbaum
Publisher:
ISBN:
Category : Intermetallic compounds
Languages : en
Pages : 22
Book Description
Publisher:
ISBN:
Category : Intermetallic compounds
Languages : en
Pages : 22
Book Description
Measurement and Interpretation of Electrical Properties of Zirconium Hydride for Hydrogen-to-metal Ratios Between 1.5 and 2
Author: P. W. Bickel
Publisher:
ISBN:
Category : Zirconium
Languages : en
Pages : 16
Book Description
Publisher:
ISBN:
Category : Zirconium
Languages : en
Pages : 16
Book Description
The Reaction of Hydrogen with Zirconium-1 and -25 W/o Uranium Alloys
Author: Harold E. Bigony
Publisher:
ISBN:
Category : Chemical kinetics
Languages : en
Pages : 34
Book Description
Publisher:
ISBN:
Category : Chemical kinetics
Languages : en
Pages : 34
Book Description
Zirconium Hydride
Author: A. L. Grunewald
Publisher:
ISBN:
Category : Hydrides
Languages : en
Pages : 40
Book Description
Publisher:
ISBN:
Category : Hydrides
Languages : en
Pages : 40
Book Description
Metallographic Study of the System ZrHx
Author: Donald Whitwham
Publisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 34
Book Description
Publisher:
ISBN:
Category : Zirconium alloys
Languages : en
Pages : 34
Book Description