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Delayed Hydride Cracking Of Zirconium Alloy Fuel Cladding
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Book Synopsis Delayed Hydride Cracking of Zirconium Alloy Fuel Cladding by : International Atomic Energy Agency
Download or read book Delayed Hydride Cracking of Zirconium Alloy Fuel Cladding written by International Atomic Energy Agency and published by . This book was released on 2010 with total page 66 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication examines the phenomena of delayed hydride cracking (DHC) in Zircaloy-4 claddings and presents the results of a coordinated research project on this subject. It discusses the circumstances and the mechanisms that lead to DHC in Zircaloy-4 cladding materials and documents the knowledge gained through an inter-laboratory comparison where the physical conditions for DHC have been studied. An advanced DHC testing methodology developed in Studsvik, Sweden, and consistent experimental data of international round-robin DHC velocity measurements in CANDU/PHWR and LWR cladding Zircaloy-4 materials are also attached.
Book Synopsis Delayed Hydride Cracking of Zirconium Alloy Fuel Cladding by :
Download or read book Delayed Hydride Cracking of Zirconium Alloy Fuel Cladding written by and published by . This book was released on 2010 with total page 66 pages. Available in PDF, EPUB and Kindle. Book excerpt: "This publication examines the phenomena of delayed hydride cracking (DHC) in Zircaloy-4 claddings and presents the results of a coordinated research project on this subject. It discusses the circumstances and the mechanisms that lead to DHC in Zircaloy-4 cladding materials and documents the knowledge gained through an inter-laboratory comparison where the physical conditions for DHC have been studied. An advanced DHC testing methodology developed in Studsvik, Sweden, and consistent experimental data of international round-robin DHC velocity measurements in CANDU/PHWR and LWR cladding Zircaloy-4 materials are also attached ... Subject Classification : 0800 - Nuclear fuel cycle and waste management. Responsible Officer : Mr. Victor Inozemtsev, NEFW."--Résumé de l'éditeur.
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.
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.
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
Book Synopsis Delayed Hydride Cracking in Zirconium Alloys in Pressure Tube Nuclear Reactors. IAEA TECDOC Series by : International Atomic Energy Agency
Download or read book Delayed Hydride Cracking in Zirconium Alloys in Pressure Tube Nuclear Reactors. IAEA TECDOC Series written by International Atomic Energy Agency and published by . This book was released on 2004 with total page 199 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report describes all of the research work undertaken as part of the IAEA coordinated research program on hydrogen and hydride induced degradation of the mechanical and physical properties of zirconium based alloys, and includes a review of the state of the art in understanding crack propagation by Delayed Hydride Cracking (DHC), and details of the experimental procedures that have produced the most consistent set of DHC rates reported in an international round-robin exercise to this date.
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.
Book Synopsis Advances in the theory of delayed hydride cracking in zirconium alloys by : S-Q. Shi
Download or read book Advances in the theory of delayed hydride cracking in zirconium alloys written by S-Q. Shi and published by . This book was released on 1996 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Prevention of delayed hydride cracking in zirconium alloys by : B. A. Cheadle
Download or read book Prevention of delayed hydride cracking in zirconium alloys written by B. A. Cheadle and published by . This book was released on 1987 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :A. H. Jackman Publisher :Mississauga, Ont. : Atomic Energy of Canada Limited, Power Projects ISBN 13 : Total Pages :24 pages Book Rating :4.:/5 (318 download)
Book Synopsis Delayed Hydrogen Cracking of Zirconium Alloy Pressure Tubes by : A. H. Jackman
Download or read book Delayed Hydrogen Cracking of Zirconium Alloy Pressure Tubes written by A. H. Jackman and published by Mississauga, Ont. : Atomic Energy of Canada Limited, Power Projects. This book was released on 1976 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Bulk Hydrides and Delayed Hydride Cracking in Zirconium Alloys by : ERIC. TULK
Download or read book Bulk Hydrides and Delayed Hydride Cracking in Zirconium Alloys written by ERIC. TULK and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
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.
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.
Book Synopsis Hydride Reorientation in Zirconium Alloy Nuclear Fuel Cladding Studied Using Synchrotron Radiation by : Jennifer Anne Jarvis
Download or read book Hydride Reorientation in Zirconium Alloy Nuclear Fuel Cladding Studied Using Synchrotron Radiation written by Jennifer Anne Jarvis and published by . This book was released on 2010 with total page 63 pages. Available in PDF, EPUB and Kindle. Book excerpt: During reactor operation, waterside corrosion of Zirconium alloy fuel cladding leads to hydrogen pickup. Hydrides platelets will normally precipitate circumferentially in the cladding. However, under temperature and load, the hydrides can reorient in the radial direction. These brittle radial hydrides can drastically reduce the ductility and the fracture toughness of the cladding. This work contains an in-situ study of hydride reorientation. Using synchrotron radiation from the Advanced Photon Source (APS) at Argonne National Laboratory, x-ray diffraction in transmission geometry was used to study a hydrogen-charged sample under mechanical and thermal load. The sample was rolled Zircaloy-2 with a hydrogen content of 96 wt.ppm. It was studied under a loading cycle with temperature cycling from 25 to 400°C and with an applied tensile stress of 100 MPa. Under two cycles of loading, partial reorientation was achieved. This diffraction data was used to perform an evaluation of the intensity, peak broadening, and peak shift of hydride peaks, in order to characterize the kinetics of reorientation. Additionally, the dissolution and precipitation temperatures were studied. Optical microscopy was used to compare the microstructure and hydride orientation before and after the experiment.
Book Synopsis Materials Ageing and Degradation in Light Water Reactors by : K L Murty
Download or read book Materials Ageing and Degradation in Light Water Reactors written by K L Murty and published by Elsevier. This book was released on 2013-02-18 with total page 441 pages. Available in PDF, EPUB and Kindle. Book excerpt: Light water reactors (LWRs) are the predominant class of nuclear power reactors in operation today; however, ageing and degradation can influence both their performance and lifetime. Knowledge of these factors is therefore critical to safe, continuous operation. Materials ageing and degradation in light water reactors provides a comprehensive guide to prevalent deterioration mechanisms, and the approaches used to handle their effects.Part one introduces fundamental ageing issues and degradation mechanisms. Beginning with an overview of ageing and degradation issues in LWRs, the book goes on to discuss corrosion in pressurized water reactors and creep deformation of materials in LWRs. Part two then considers materials’ ageing and degradation in specific LWR components. Applications of zirconium alloys in LWRs are discussed, along with the ageing of electric cables. Materials management strategies for LWRs are then the focus of part three. Materials management strategies for pressurized water reactors and VVER reactors are considered before the book concludes with a discussion of materials-related problems faced by LWR operators and corresponding research needs.With its distinguished editor and international team of expert contributors, Materials ageing and degradation in light water reactors is an authoritative review for anyone requiring an understanding of the performance and durability of this type of nuclear power plant, including plant operators and managers, nuclear metallurgists, governmental and regulatory safety bodies, and researchers, scientists and academics working in this area. Introduces the fundamental ageing issues and degradation mechanisms associated with this class of nuclear power reactors Considers materials ageing and degradation in specific light water reactor components, including properties, performance and inspection Chapters also focus on material management strategies
Download or read book Zirconium written by Oswald Kubaschewski and published by . This book was released on 1976 with total page 268 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis The Effect of Microstructure on Delayed Hydride Cracking Behavior of Zircaloy-4 Fuel Cladding--An International Atomic Energy Agency Coordinated Research Program by : C. Coleman
Download or read book The Effect of Microstructure on Delayed Hydride Cracking Behavior of Zircaloy-4 Fuel Cladding--An International Atomic Energy Agency Coordinated Research Program written by C. Coleman and published by . This book was released on 2010 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt: The rate of delayed hydride cracking (DHC) has been measured in Zircaloy-4 fuel cladding in several metallurgical conditions using the pin-loading tension technique. In light water reactor (LWR) cladding in the cold-worked and cold-worked and stress-relieved conditions, the cracking rate followed Arrhenius behavior up to about 280 °C, but at higher temperatures the rate declined with no cracking above 300°C. Non-LWR cladding appeared to behave in the same manner. In LWR cladding in the recrystallized condition, the cracking rate was highly variable because it depended on KI within the test range up to 25 MPa√m, whereas in the other LWR claddings, cracking rate was independent of KI, indicating that KIH was below 11 MPa√m. The main role of microstructure was to control the material strength; the cracking rate increased as the strength increased. Although all the claddings had a radial texture, it did not protect the cladding from DHC. The DHC fracture surface consisted of flat broken hydrides, often in arcs, but no striations were observed, except in one specimen subjected to thermal cycles.
