Zirconium in the Nuclear Industry

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Publisher : ASTM International
ISBN 13 : 0803128959
Total Pages : 891 pages
Book Rating : 4.8/5 (31 download)

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Book Synopsis Zirconium in the Nuclear Industry by : Gerry D. Moan

Download or read book Zirconium in the Nuclear Industry written by Gerry D. Moan and published by ASTM International. This book was released on 2002 with total page 891 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Temperature and Hydrogen Concentration Limits for Delayed Hydride Cracking in Irradiated Zircaloy

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ISBN 13 :
Total Pages : 19 pages
Book Rating : 4.:/5 (125 download)

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Book Synopsis Temperature and Hydrogen Concentration Limits for Delayed Hydride Cracking in Irradiated Zircaloy by : JS. Schofield

Download or read book Temperature and Hydrogen Concentration Limits for Delayed Hydride Cracking in Irradiated Zircaloy written by JS. Schofield and published by . This book was released on 2002 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt: Critical temperatures for delayed hydride cracking (DHC) initiation during cooling (TRIT) and crack arrest during heating (TDAT) have been measured in experiments on specimens from a Zircaloy-2 electron beam weld irradiated to a fluence of 3 to 5 > 1025 n • m-2 (E > 1 MeV) and then hydrided to concentrations of 35 and 55 ppm. The experimental observations are shown to be consistent with a simple model based on previously determined hydrogen terminal solid solubility data for dissolution and precipitation, which describes conditions for sustained hydride precipitation at the crack tip. When plotted against bulk hydrogen concentration in solution, both TRIT and TDAT fall below the dissolution solvus temperature and above the precipitation solvus temperature. A key assumption in the model is that, while the local crack tip stress concentration causes local enhancement of the hydrogen concentration in solution, the hydride precipitation solvus is unaffected by stress. The good agreement obtained between measured and predicted critical temperatures provides strong support for this assumption.

Hydrogen concentration limit and critical temperatures for delayed hydride cracking in zirconium alloys

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ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)

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Book Synopsis Hydrogen concentration limit and critical temperatures for delayed hydride cracking in zirconium alloys by : S.-Q. Shi

Download or read book Hydrogen concentration limit and critical temperatures for delayed hydride cracking in zirconium alloys written by S.-Q. Shi and published by . This book was released on 1994 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nucirc2 is a steady state thermohydraulic code designed to analyze the primary heat transport system of a candu nuclear reactor for a variety of operating conditions. this document describes the nucirc2 capabilities and options as well as the information necessary for the preparation of the input data.

Delayed Hydride Cracking in Irradiated Zircaloy Cladding

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Publisher :
ISBN 13 :
Total Pages : 16 pages
Book Rating : 4.:/5 (125 download)

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Book Synopsis Delayed Hydride Cracking in Irradiated Zircaloy Cladding by : K. Pettersson

Download or read book Delayed Hydride Cracking in Irradiated Zircaloy Cladding written by K. Pettersson and published by . This book was released on 2000 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: Slow stable crack growth by a mechanism identified as a form of delayed hydride cracking has been studied on irradiated Zircaloy cladding. The background to the investigation was the formation of long axial cracks in defected fuel rods. Post-irradiation examination of such fuel rods has indicated that precipitation and subsequent cracking of hydrides at the tips of the long cracks has played an important role in the crack growth process. The present investigation conducted on irradiated cladding with hydrogen concentrations above about 500 ppm has demonstrated that a hydrogen-induced crack growth process can occur in such material. In the laboratory it was necessary to subject the samples to an overtemperature cycle in order to initiate crack growth after fatigue precracking. It was also observed that an incubation time on the order of 20 h was necessary before crack growth started. The crack growth rates were strongly dependent on the applied stress intensity factor K in a narrow range above a threshold value KIH, which was about 10 MPa?m, Stage I. The growth rate then reached a plateau value when it was independent of K, Stage II. This plateau value was about 10-6 m/s at 300°C and about 2 x 10-7 m/s at 200°C. This temperature dependence is consistent with a mechanism based on stress-induced diffusion of hydrogen at the stress concentration of the crack tip. Metallographic and fractographic observations suggest that the details of the mechanism can be best described as a localized reduction of fracture toughness due to reorientation of hydrides so that they become perpendicular to the applied stress in the region of the crack tip. This is somewhat in contrast to previous DHC mechanisms in which longer-range diffusion of hydrogen to one large hydride at the crack tip is usually modeled. The difference is that in the present case the hydride content is higher and therefore more hydrides are present.

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

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Publisher : Springer Science & Business Media
ISBN 13 : 1447141954
Total Pages : 475 pages
Book Rating : 4.4/5 (471 download)

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Book Synopsis The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components by : Manfred P. Puls

Download or read book The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components written by Manfred P. Puls and published by Springer Science & Business Media. This book was released on 2012-08-04 with total page 475 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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

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Publisher :
ISBN 13 :
Total Pages : 976 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Zirconium in the Nuclear Industry by :

Download or read book Zirconium in the Nuclear Industry written by and published by . This book was released on 1998 with total page 976 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Comprehensive Structural Integrity

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Publisher : Elsevier
ISBN 13 : 0080490735
Total Pages : 4647 pages
Book Rating : 4.0/5 (84 download)

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Book Synopsis Comprehensive Structural Integrity by : Ian Milne

Download or read book Comprehensive Structural Integrity written by Ian Milne and published by Elsevier. This book was released on 2003-07-25 with total page 4647 pages. Available in PDF, EPUB and Kindle. Book excerpt: The aim of this major reference work is to provide a first point of entry to the literature for the researchers in any field relating to structural integrity in the form of a definitive research/reference tool which links the various sub-disciplines that comprise the whole of structural integrity. Special emphasis will be given to the interaction between mechanics and materials and structural integrity applications. Because of the interdisciplinary and applied nature of the work, it will be of interest to mechanical engineers and materials scientists from both academic and industrial backgrounds including bioengineering, interface engineering and nanotechnology. The scope of this work encompasses, but is not restricted to: fracture mechanics, fatigue, creep, materials, dynamics, environmental degradation, numerical methods, failure mechanisms and damage mechanics, interfacial fracture and nano-technology, structural analysis, surface behaviour and heart valves. The structures under consideration include: pressure vessels and piping, off-shore structures, gas installations and pipelines, chemical plants, aircraft, railways, bridges, plates and shells, electronic circuits, interfaces, nanotechnology, artificial organs, biomaterial prostheses, cast structures, mining... and more. Case studies will form an integral part of the work.

Prevention of Delayed Hydride Cracking in Zirconium Alloys

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Publisher :
ISBN 13 :
Total Pages : 17 pages
Book Rating : 4.:/5 (125 download)

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Book Synopsis Prevention of Delayed Hydride Cracking in Zirconium Alloys by : JFR Ambler

Download or read book Prevention of Delayed Hydride Cracking in Zirconium Alloys written by JFR Ambler and published by . This book was released on 1987 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: Zirconium alloys are susceptible to a mechanism for crack initiation and propagation called delayed hydride cracking. From a review of component failures and experimental results, we have developed the requirements for preventing this cracking. The important parameters for cracking are hydrogen concentration, flaws, and stress; each should be minimized. At the design and construction stages hydrogen pickup has to be controlled, quality assurance needs to be at a high enough level to ensure the absence of flaws, and residual stresses must be eliminated by careful fabrication and heat treatment.

Delayed Hydride Cracking in Zirconium Alloys in Pressure Tube Nuclear Reactors

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Publisher : IAEA
ISBN 13 :
Total Pages : 102 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Delayed Hydride Cracking in Zirconium Alloys in Pressure Tube Nuclear Reactors by : International Atomic Energy Agency

Download or read book Delayed Hydride Cracking in Zirconium Alloys in Pressure Tube Nuclear Reactors written by International Atomic Energy Agency and published by IAEA. This book was released on 2004 with total page 102 pages. Available in PDF, EPUB and Kindle. Book excerpt: Dated October 2004. With CD-ROM containing additional information inside back cover

Internal Zirconium Hydride Formation in Zircaloy Fuel Element Cladding Under Irradiation

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Publisher :
ISBN 13 :
Total Pages : 52 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Internal Zirconium Hydride Formation in Zircaloy Fuel Element Cladding Under Irradiation by : J. M. Markowitz

Download or read book Internal Zirconium Hydride Formation in Zircaloy Fuel Element Cladding Under Irradiation written by J. M. Markowitz and published by . This book was released on 1963 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Effect of Hydrogen and Hydride Morphology on the Tensile Properties of Zircaloy-2

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Publisher :
ISBN 13 :
Total Pages : 54 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Effect of Hydrogen and Hydride Morphology on the Tensile Properties of Zircaloy-2 by : W. J. Babyak

Download or read book Effect of Hydrogen and Hydride Morphology on the Tensile Properties of Zircaloy-2 written by W. J. Babyak and published by . This book was released on 1963 with total page 54 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Is Spent Nuclear Fuel Immune from Delayed Hydride Cracking During Dry Storage? An IAEA Coordinated Research Project

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Publisher :
ISBN 13 :
Total Pages : 28 pages
Book Rating : 4.:/5 (125 download)

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Book Synopsis Is Spent Nuclear Fuel Immune from Delayed Hydride Cracking During Dry Storage? An IAEA Coordinated Research Project by : Christopher E. Coleman

Download or read book Is Spent Nuclear Fuel Immune from Delayed Hydride Cracking During Dry Storage? An IAEA Coordinated Research Project written by Christopher E. Coleman and published by . This book was released on 2018 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt: Delayed hydride cracking (DHC) has been responsible for cracking in zirconium alloy pressure tubes and fuel cladding and is a concern for spent fuel storage. For cracking to start, sufficient hydrogen must be present for hydride to form at a flaw tip and the local tensile stress must be sufficiently large to crack the hydride (a crack will not extend if the threshold in the stress intensity factor, KIH, is not exceeded. A high-temperature limit exists when the yield stress of the cladding alloy becomes too low to crack the hydride. In this paper we describe measurements of KIH and the crack growth rate, V, in unirradiated Zircaloy-4 fuel cladding containing approximately 130 ppm hydrogen in the cold-worked stress-relieved condition representing pressurized water reactors (PWRs) and pressurized heavy-water (PHWR) reactors. Four methods are used to evaluate KIH. The test specimen and fixture used in these methods was the pin-loading tension configuration. The test temperature ranged from 227 to 315°C. The mean value of KIH below 280°C had little temperature dependence; it was about 5.5 MPa?m in the PWR cladding and slightly higher at 7 MPa?m in the PHWR material. At higher test temperatures, KIH increased dramatically to more than 12 MPa?m, whereas the crack growth rate declined toward zero. This behavior suggests that unirradiated Zircaloy-4 fuel cladding is immune from DHC above about 320°C; this temperature may be increased to 360°C by irradiation. The implications for spent fuel storage are that during early storage when the temperatures are high, any flaw will not extend by DHC, whereas at low temperatures, after many years of storage, flaws would have to be very large, approaching through wall, before being extended by DHC. To date, spent nuclear fuel is not known to have failed by DHC during storage, confirming the inference.

Hydride Precipitation Crack Propagation in Zircaloy Cladding During a Decreasing Temperature History

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Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (682 download)

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Book Synopsis Hydride Precipitation Crack Propagation in Zircaloy Cladding During a Decreasing Temperature History by :

Download or read book Hydride Precipitation Crack Propagation in Zircaloy Cladding During a Decreasing Temperature History written by and published by . This book was released on 2000 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: An assessment of safety, design, and cost tradeoff issues for short (ten to fifty years) and longer (fifty to hundreds of years) interim dry storage of spent nuclear fuel in Zircaloy rods shall address potential failures of the Zircaloy cladding caused by the precipitation response of zirconium hydride platelets. If such assessment analyses are to be done rigorously, they will be necessarily complex because the precipitation response of zirconium hydride platelets is a stochastic functional of hydrogen concentration, temperature, stress, fabrication defect/texture structures, and flaw sizes of the cladding. Thus, there are, and probably always will be, zirhydride questions to analytically and experimentally resolve concerning the consistency, the completeness, and the certainty of models, data, the initial and the time-dependent boundary conditions. Some resolution of these questions will be required in order to have a defensible preference and tradeoffs decision analysis for assessing risks and consequences of the potential zirhydride induced cladding failures during dry storage time intervals. In the following brief discussion, one of these questions is posed as a consequence of an anomaly described in data reproducibility that was reported in the results of tests for hydrogen induced delayed cracking. The testing anomaly consisted of observing a significant differential in the measurable crack velocities (quasi-steady state at a prescribed load and temperature values) that depended on the approach direction, from above or from below, to the test temperature value. The testing method used was restricted to approaching a prescribed test temperature value from above. This anomaly illustrates the known thermodynamic non-equilibrium processes in the precipitation kinetics of zirhydride platelets that are dependent on temperature and stress histories. Detailed solubility limits of hydrogen in Zircaloy as a function of temperature, in terms of zirhydride precipitation and zirhydride dissolution solubility curves, were reported recently. In addition, other tests to evaluate the influence of an applied stress state on zirhydride precipitation kinetics have also been recently reported.

Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems

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Publisher : John Wiley & Sons
ISBN 13 : 1118787773
Total Pages : 1776 pages
Book Rating : 4.1/5 (187 download)

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Book Synopsis Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems by : Steve Bruemmer

Download or read book Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems written by Steve Bruemmer and published by John Wiley & Sons. This book was released on 2013-10-18 with total page 1776 pages. Available in PDF, EPUB and Kindle. Book excerpt: This collection presents an exchange of ideas among scientists and engineers about the economic and safety concerns surrounding environmentally induced materials problems which lead to nuclear power plant outages. Scientists and engineers concerned with the environmental degradation processes (corrosion, mechanical, and radiation effects) present their latest results on such topics as life extension/relicensing and materials problems associated with spent fuel storage and radioactive waste disposal. This collection will be of interest to utility engineers, reactor vendor engineers, plant architect engineers, researchers concerned with materials degradation, and consultants involved in design, construction, and operation of water reactors.

Zirconium in the Nuclear Industry

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Publisher : ASTM International
ISBN 13 : 0803124996
Total Pages : 953 pages
Book Rating : 4.8/5 (31 download)

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Book Synopsis Zirconium in the Nuclear Industry by : George P. Sabol

Download or read book Zirconium in the Nuclear Industry written by George P. Sabol and published by ASTM International. This book was released on 2000 with total page 953 pages. Available in PDF, EPUB and Kindle. Book excerpt:

The Influence of Temperature and Yield Strength on Delayed Hydride Cracking in Hydrided Zircaloy-2

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Publisher :
ISBN 13 :
Total Pages : 11 pages
Book Rating : 4.:/5 (125 download)

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Book Synopsis The Influence of Temperature and Yield Strength on Delayed Hydride Cracking in Hydrided Zircaloy-2 by : P. Efsing

Download or read book The Influence of Temperature and Yield Strength on Delayed Hydride Cracking in Hydrided Zircaloy-2 written by P. Efsing and published by . This book was released on 1996 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: To determine if delayed hydride cracking (DHC) can be the cause of the long axial cracks occasionally found in BWR fuel cladding, a systematic study of DHC in Zircaloy cladding has begun. In the initial stage of the project, a test technique was developed and applied to unirradiated samples of Zircaloy. The present study includes an investigation of the influence of the yield strength and temperature on the crack growth rate and the threshold stress intensity that must be exceeded before cracking begins.

Hydrogen Effects on Zircaloy-2 Tensile Properties

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Publisher :
ISBN 13 :
Total Pages : 108 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Hydrogen Effects on Zircaloy-2 Tensile Properties by : H. H. Burton

Download or read book Hydrogen Effects on Zircaloy-2 Tensile Properties written by H. H. Burton and published by . This book was released on 1959 with total page 108 pages. Available in PDF, EPUB and Kindle. Book excerpt: