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Terminal Solid Solubility Of Hydrogen In Zircaloy 2
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Book Synopsis Terminal Solid Solubility of Hydrogen in Zircaloy-2 by : Canadian General Electric Company Limited
Download or read book Terminal Solid Solubility of Hydrogen in Zircaloy-2 written by Canadian General Electric Company Limited and published by . This book was released on 1966 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis The Terminal Solid Solubility of Hydrogen in Zirconium Alloys by : JS. Schofield
Download or read book The Terminal Solid Solubility of Hydrogen in Zirconium Alloys written by JS. Schofield and published by . This book was released on 2000 with total page 23 pages. Available in PDF, EPUB and Kindle. Book excerpt: An experimental program has been carried out to measure the terminal solid solubility (TSS) of hydrogen in Zircaloy. Unirradiated electron beam (EB) welded Zircaloy-2, EB-welded Zircaloy-4, Zircaloy-2 pressure tube, cold-worked ?-quenched Zircaloy-2 forging, oxygen-strengthened tungsten inert gas (TIG) welded Zircaloy-4, and irradiated welded Zircaloy-2, welded Zircaloy-4, and Zircaloy-2 pressure tube materials were tested. A differential scanning calorimetry technique was used to measure the dissolution and precipitation temperatures for a range of hydrogen concentrations.
Book Synopsis Hydriding of Zircaloy-2 by : Myra S. Feldman
Download or read book Hydriding of Zircaloy-2 written by Myra S. Feldman and published by . This book was released on 1963 with total page 156 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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:
Book Synopsis Hydrogen Solubility and Microstructural Changes in Zircaloy-4 Due to Neutron Irradiation by : P. Vizcaíno
Download or read book Hydrogen Solubility and Microstructural Changes in Zircaloy-4 Due to Neutron Irradiation written by P. Vizcaíno and published by . This book was released on 2011 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt: The present work deals with two essential degradation mechanisms of zirconium alloys: Hydrogen behavior and microstructural transformations due to neutron irradiation. The studies were carried out by using samples taken from Zircaloy-4 components, which remained for 14 years in the Atucha I pressurized heavy water reactor, accumulating neutron fluences of up to 1022 neutrons/cm2. A hydrogen/deuterium solubility increase was observed in both dissolution and precipitation processes. With the aim to follow this evolution with radiation damage recovery, the irradiated samples were annealed for different periods at 350 and 400°C in a differential scanning calorimeter (DSC). These temperatures were chosen to reproduce those reached by spent fuels in the early stages of the dry storage (DS). Between intervals, the terminal solid solubility temperatures in dissolution (TTSSd) and in precipitation (TTSSp) were determined. They were also determined after additional annealing at 500 and 600°C, trying to simulate long periods at DS. The hydride morphology and the metallurgical state of the Zr(Fe, Cr)2 second-phase particles (SPPs) were followed between annealing by optical microscopy, analytical electron microscopy, synchrotron light X-ray diffraction4 (SXRD), and DSC. As a brief summary, we found from the first to the last run of the annealing sequence an increase of 55°C in TTSSd and 40°C in TTSSp on average. The optical and transmission electron microscopies (TEM) indicate that in the material in the irradiated condition, exists a hydride size distribution of four orders of magnitude, from 10 nm to 100 ?m, but biased to sizes smaller than 5 ?m. A complete amorphisation of the SPPs was observed in high fluence samples by TEM and SXRD. Similar TEM observations made in irradiated samples annealed above 400°C show a re-precipitation process of nano-SPPs forming clusters. The re-precipitation is affected by kinetics: The SPPs crystallization temperature, Tc, rises from 450 to 500°C as the heating rate increases from 5 to 20°C/min. The measured heat of crystallization was 27.3±2.1 kJ/mol (Fe + Cr).
Author :Atomic Energy of Canada Limited Publisher :Pinawa, Man. : Whiteshell Nuclear Research Establishment ISBN 13 : Total Pages :32 pages Book Rating :4.:/5 (158 download)
Book Synopsis Determination of the Terminal Solid Solubility of Hydrogen in Zirconium at Low Hydrogen Concentrations by : Atomic Energy of Canada Limited
Download or read book Determination of the Terminal Solid Solubility of Hydrogen in Zirconium at Low Hydrogen Concentrations written by Atomic Energy of Canada Limited and published by Pinawa, Man. : Whiteshell Nuclear Research Establishment. This book was released on 1978 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 Effect of Irradiation on Terminal Solid Solubility of Hydrogen in Zr-2.5Nb by : Heidi M. Nordin
Download or read book Effect of Irradiation on Terminal Solid Solubility of Hydrogen in Zr-2.5Nb written by Heidi M. Nordin and published by . This book was released on 2018 with total page 31 pages. Available in PDF, EPUB and Kindle. Book excerpt: Knowledge of the temperature dependence of hydrogen solubility is used to define the conditions necessary for brittle hydrides to be present in reactor components during service. The terminal solid solubility (TSS) of hydrogen is affected by several factors, including irradiation, cold work, and decomposition of the ? phase in Zr-2.5Nb. TSS temperatures for specimens irradiated in Osiris, Halden, and CANDU® reactors are reported. TSS was measured on Zr-2.5Nb specimens using differential scanning calorimetry (DSC) to complete four heat-up/cool-down cycles (heat to a peak temperature and cool to room temperature at a rate of 10°C/min) followed by a 1-h anneal at 500°C, and then four more heat-up/cool-down cycles. As with Zircaloy, irradiation slightly decreases the TSS temperatures, but subsequent annealing increases them. These changes are attributed to an initial effect of irradiation damage and reconstitution of the ? phase and reversal of these effects by annealing, as indicated by X-ray diffraction data showing reduced dislocation density and higher ?-phase volume fraction after the specimens were annealed.
Book Synopsis DETERMINATION OF THE TERMINAL SOLID SOLUBILITY OF HYDROGEN IN ZIRCONIUM AT LOW HYDROGEN CONCENTRATIONS. by : Atomic Energy of Canada Limited
Download or read book DETERMINATION OF THE TERMINAL SOLID SOLUBILITY OF HYDROGEN IN ZIRCONIUM AT LOW HYDROGEN CONCENTRATIONS. written by Atomic Energy of Canada Limited and published by . This book was released on 1975 with total page 39 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Determination of the Terminal Solid Solubility of Hydrogen in Zirconium at Low Hydrogen Concentratrations by : C. D. Cann
Download or read book Determination of the Terminal Solid Solubility of Hydrogen in Zirconium at Low Hydrogen Concentratrations written by C. D. Cann and published by . This book was released on 1978 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Hydrogen Distribution in Zircaloy Under a Temperature Gradient by : Evrard Lacroix
Download or read book Hydrogen Distribution in Zircaloy Under a Temperature Gradient written by Evrard Lacroix and published by . This book was released on 2016 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: During normal operation in nuclear reactors, the nuclear fuel cladding corrodes as a result of exposure to high temperature cooling water. During this process, hydrogen can enter the zirconium-alloy of the fuel cladding, and under proper conditions, precipitate as brittle hydride platelets which can severely impact cladding ductility and fracture toughness. Hydrogen tends to migrate to and precipitate at colder spots. Because high local hydride concentrations increase the risk of cladding failure, it is important to predict the local hydrogen distribution. Hydrogen transport depends on different phenomena. Even though migration can only occur when the hydrogen is in solid solution, the cladding temperatures during operating condition allow a portion of the hydrogen to be in solid solution. Therefore, as hydrogen is picked up during the corrosion reaction between the cladding and the coolant, it can migrate following Ficks law and the Soret effect. Once the local hydrogen content reaches the terminal solid solubility for precipitation, the hydrogen will start precipitating as zirconium hydride. Previous work in our laboratory implemented a model that describes these different phenomena, into the 3D fuel performance code BISON. A first attempt to benchmark this model has been made in this study by comparing the results given by BISON to the hydrogen distribution measured in a nuclear fuel rod, which underwent a five cycle exposure at the Gravelines nuclear power plant. This was feasible because of the very detailed information about that reactor and fuel pin were available from the thesis of J.-H. Zhang in 1992. The benchmark performed with BISON showed very good agreement between the calculations experimental observation.The calculation above used a value of the precipitation kinetics parameter 2 based on a fit that ignored discrepancies in the early part of the precipitation process. The calculation was revised according to a new model. The new model, which assumes an initial dependence of the precipitation rate on (C_ss-TSS_p )^2 , provides a better fit for this date and we believe a more precise value of 2, which varies mildly with temperature.
Book Synopsis Review of Zircaloy-2 and Zircaloy-4 Properties Relevant to N.S. Savannah Reactor Design by : C. L. Whitmarsh
Download or read book Review of Zircaloy-2 and Zircaloy-4 Properties Relevant to N.S. Savannah Reactor Design written by C. L. Whitmarsh and published by . This book was released on 1962 with total page 74 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Hydrogen Redistribution in Thin Plates of Zirconium Under Large Thermal Gradients by : J. M. Markowitz
Download or read book Hydrogen Redistribution in Thin Plates of Zirconium Under Large Thermal Gradients written by J. M. Markowitz and published by . This book was released on 1958 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis The terminal solid solubility of hydrogen and deuterium in zr-2.5 nb alloys by : Z. L. Pan
Download or read book The terminal solid solubility of hydrogen and deuterium in zr-2.5 nb alloys written by Z. L. Pan and published by . This book was released on 1995 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Materials written by and published by . This book was released on 1969 with total page 304 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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.
Book Synopsis Scientific and Technical Aerospace Reports by :
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1966 with total page 1492 pages. Available in PDF, EPUB and Kindle. Book excerpt:
