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 ...
Author: Manfred P. Puls
Publisher: Springer Science & Business Media
Category: Technology & Engineering
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: Delayed Hydride Cracking. London: Springer-Verlag. 190. Colas,
K.B., Motta, A.T., Almer, J.D., et al., 2010. In situ study of hydride precipitation
kinetics and ...
Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials 2e provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field
 R.L. Cowan, J. Varela, S.E. Garcia, The effect of on-line noble metal addition
on the shutdown dose rates of boiling ...  M.P. Puls, The effect of hydrogen
and hydrides on the integrity of zirconium alloy components: delayed hydride ...
Author: Robert Odette
Category: Technology & Engineering
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.
Michael A. Gharghouri Abstract Hydrogen scatters neutrons strongly and
incoherently, which makes neutrons very sensitive to the ... to various types of
failure, such as Delayed Hydride Cracking (Puls, The Effect of Hydrogen and Hydrides on the Integrity of Zirconium M.A. ... Scattering Applications and
Techniques, DOI 10.1007/978-3-319-22792-4_8 227 Alloy Components:
Delayed Hydride Cracking.
Author: Helmut Fritzsche
Category: Technology & Engineering
This book provides a comprehensive overview of the main nuclear characterization techniques used to study hydrogen absorption and desorption in materials. The various techniques (neutron scattering, nuclear magnetic resonance, ion-beams, positron annihilation spectroscopy) are explained in detail, and a variety of examples of recent research projects are given to show the unique advantage of these techniques to study hydrogen in materials. Most of these nuclear techniques require very specialized instrumentation, and there are only a handful of these instruments available worldwide. Therefore, the aim of this book is to reach out to a readership with a very diverse background in the physical sciences and engineering and a broad range of hydrogen-related research interests. The same technique can be used by researchers interested in the improvement of the performance of hydrogen storage materials and by those focused on hydrogen ingress causing embrittlement of metals. The emphasis of this book is to provide tutorial material on how to use nuclear characterization techniques for the investigation of hydrogen in materials – information that cannot readily be found in conference and regular research papers. Provides a comprehensive overview of nuclear techniques used for hydrogen-related research Explains all nuclear techniques in detail for the non-expert Covers the whole range of hydrogen-related research Features chapters written by world-renowned experts in nuclear technique and hydrogen-related research
Extreme variations in local hydrogen absorption in fuel cladding give rise to "
sunburst" hydrides, which may be a primary cause of ... from inside the fuel rod,
or a cause of severe secondary failures following a breach of cladding integrity
by some other mechanism [/]. ... In order to assess the effect of hydriding on the
mechanical properties of a zirconium alloy component, it is necessary to
determine the ...
Effects of texture on the habit plane and the threshold stress for hydride
reorientation are also discussed. ... Hydrides also play important roles in the
structural integrity of other types of Zr-alloy components such as guide tubes,
spacer grids, and pressure tubes. ... hydrides play crucial roles, such as delayed hydride cracking [1,5], corrosion hydride cracking , and hydrogen-assisted
localized shear [2,3].
Author: Gerry D. Moan
Publisher: ASTM International
Category: Nuclear fuel claddings
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.
is hydrogen embrittlement1 associated with the precipitation of zirconium hydride
. ... Significant from an engineering standpoint is the effect of total hydrogen and hydride morphology on the necking strain and the notched strength of Zircaloy-2.
... loss of necking strain.5'6 Therefore, the value of necking strain becomes
important in assessing the integrity of Zircaloy-2 components in reactor service. ...
Factors Affecting Oxidation and Hydriding of Zirconium Alloys, *S. B. Dalgaard (
Author: Canadian Institute of Mining and MetallurgyPublish On: 1978
Alternatively , hydrogen in solid solution has a negligible effect on mechanical
properties of the alloys . In the commercial production of zirconium alloys some hydrogen , about 10 - 25 wt ppm , remains as an impurity . ... all the zirconium alloy components contain hydrides when the reactor is at ambient temperature
during shutdown , and in varying degrees ... the two distinct hydrogen - related
phenomena which provide a threat to the integrity of materials in sour
environments typically ...
Author: Canadian Institute of Mining and Metallurgy
Hydride blister formation involves the coupled action of gradients in temperature
and hydrogen concentration , while ... Crack Hydrogen driven to crack tip by
stress gradient promotes further cracking b ) delayed hydride cracking
INTRODUCTION Although zirconium alloys are able to ... Quantification of the effects of blister growth and DHC on the structural integrity of Zr - Nb components
is necessary to ...
Publisher: American Society of Mechanical Engineers
The effect of hydrides oriented in both the circumferential and radial directions is
discussed, and it is concluded that the hydrogen absorbed during a 30 year life
should have no significant effect on the critical defect size. ... and the use of
periodic cold pressure tests is considered as a means of demonstrating pressure
tube integrity. KEY WORDS: Zircaloy, embrittlement, irradiation, defects, fractures
(materials), defect growth rates, pressure measurement, zirconium alloys The