Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry PDF Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 849

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Book Description

Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry PDF Author:
Publisher: ASTM International
ISBN:
Category :
Languages : en
Pages : 849

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Book Description


Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry PDF Author: Leo F. P. Van Swam
Publisher: ASTM International
ISBN: 0803111991
Category : Nuclear fuel claddings
Languages : en
Pages : 781

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Reactor Materials

Reactor Materials PDF Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 192

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Reactor Core Materials

Reactor Core Materials PDF Author:
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 196

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Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1078

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Diffusion and Defect Data

Diffusion and Defect Data PDF Author:
Publisher:
ISBN:
Category : Crystals
Languages : en
Pages : 362

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The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components

The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components PDF Author: Manfred P. Puls
Publisher: Springer Science & Business Media
ISBN: 1447141954
Category : Science
Languages : en
Pages : 475

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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.

Metals Abstracts

Metals Abstracts PDF Author:
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 1558

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Titanium and Titanium Alloys

Titanium and Titanium Alloys PDF Author: Christoph Leyens
Publisher: John Wiley & Sons
ISBN: 3527605207
Category : Technology & Engineering
Languages : de
Pages : 532

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Book Description
This handbook is an excellent reference for materials scientists and engineers needing to gain more knowledge about these engineering materials. Following introductory chapters on the fundamental materials properties of titanium, readers will find comprehensive descriptions of the development, processing and properties of modern titanium alloys. There then follows detailed discussion of the applications of titanium and its alloys in aerospace, medicine, energy and automotive technology.

Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry PDF 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