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.

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.

Zirconium in the Nuclear Industry

Zirconium in the Nuclear Industry PDF Author: Gerry D. Moan
Publisher: ASTM International
ISBN: 0803128959
Category : Nuclear fuel claddings
Languages : en
Pages : 891

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Book Description
Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.

Mechanical Behaviour of Materials - VI

Mechanical Behaviour of Materials - VI PDF Author: M. Jono
Publisher: Elsevier
ISBN: 1483294137
Category : Technology & Engineering
Languages : en
Pages : 3510

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Book Description
Significant progress in the science and technology of the mechanical behaviour of materials has been made in recent years. The greatest strides forward have occurred in the field of advanced materials with high performance, such as ceramics, composite materials, and intermetallic compounds. The Sixth International Conference on Mechanical Behaviour of Materials (ICM-6), taking place in Kyoto, Japan, 29 July - 2 August 1991 addressed these issues. In commemorating the fortieth anniversary of the Japan Society of Materials Science, organised by the Foundation for Advancement of International Science and supported by the Science Council of Japan, the information provided in these proceedings reflects the international nature of the meeting. It provides a valuable account of recent developments and problems in the field of mechanical behaviour of materials.

Hydrogen Effects in Materials

Hydrogen Effects in Materials PDF Author: Anthony W. Thompson
Publisher: John Wiley & Sons
ISBN: 1118803272
Category : Technology & Engineering
Languages : en
Pages : 1090

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Book Description
Proceedings of the Fifth International Conference on the Effect of Hydrogen on the Behavior of Materials sponsored by the Structural Materials Division (SMD) Mechanical Metallurgy and Corrosion & Environmental Effects Committees of The Minerals, Metals & Materials Society held at Jackson Lake Lodge, Moran, Wyoming, September 11-14, 1994.

Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 972

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Book Description


Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1090

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Book Description


ERDA Energy Research Abstracts

ERDA Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1028

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Corrosion Characteristics, Mechanisms and Control Methods of Candidate Alloys in Sub- and Supercritical Water

Corrosion Characteristics, Mechanisms and Control Methods of Candidate Alloys in Sub- and Supercritical Water PDF Author: Donghai Xu
Publisher: Springer Nature
ISBN: 9811655251
Category : Science
Languages : en
Pages : 248

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Book Description
This book aims to provide comprehensive and systematic introduction and summary of corrosion characteristics, mechanisms, and control methods of candidate alloys in sub- and supercritical water environment. First of all, corrosion types of candidate alloys and the effects of major alloying elements on corrosion resistance of potential alloys in sub- and supercritical water are compared and analyzed. At the same time, research status of candidate materials, and development and application trends of several corrosion-resistant alloys are summarized. Then, corrosion characteristics of Ni-Cr, Ni-Cr-Mo, Ni-Fe-Cr and Ni-Fe-Cr-Mo-Cu corrosion-resistant alloys, FeCrAl alloy, and Zircaloy are discussed in detail, including the corrosion rate, the structure and composition of oxide film, and the effects of various surface treatment processes, etc. More specifically, it also investigates corrosion behavior of Ni-based alloy, Fe-Ni-based, and stainless steels in supercritical water. The effects of aggressive species on the corrosion behavior of Ni-base alloys are also explored in supercritical water. Readers will further discover the total corrosion processes and mechanisms of typical candidate alloys in sub- and supercritical water environment. Finally, the work explores the corrosion control methods such as ceramic coatings and passivation processes in supercritical water oxidation and in subcritical water, respectively. Future challenges and development trends of corrosion research of candidate materials in sub- and supercritical water environments are covered at the end of this book. It offers valuable reference for theoretically guiding material selection and design and operating parameter optimization of key equipment in the sub- and supercritical water technologies. The book is written for senior undergraduates, graduate students, scholars, and researchers who are interested in corrosion behavior of candidate materials of supercritical water oxidation system, supercritical water gasification system, and nuclear reactor.

Structural Alloys for Nuclear Energy Applications

Structural Alloys for Nuclear Energy Applications PDF Author: Robert Odette
Publisher: Newnes
ISBN: 012397349X
Category : Technology & Engineering
Languages : en
Pages : 676

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Book Description
High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors' unique personal insight from decades of frontline research, engineering and management. - Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. - Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. - Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.

Power Reactor Technology

Power Reactor Technology PDF Author:
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 1084

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Book Description