Download or read book Method to Predict Relative Hydriding Within a Group of Zirconium Alloys Under Nuclear Irradiation written by and published by . This book was released on 1990 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: An out-of-reactor method for screening to predict relative in-reactor hydriding behavior of zirconium-bsed materials is disclosed. Samples of zirconium-based materials having different composition and/or fabrication are autoclaved in a relatively concentrated (0.3 to 1.0M) aqueous lithium hydroxide solution at constant temperatures within the water reactor coolant temperature range (280.degree. to 316.degree. C.). Samples tested by this out-of-reactor procedure, when compared on the basis of the ratio of hydrogen weight gain to oxide weight gain, accurately predict the relative rate of hyriding for the same materials when subject to in-reactor (irradiated) corrision.

Download or read book A Laboratory Method to Predict Hydriding Properties of Zirconium Alloys Under Irradiation written by FS. Gerber and published by . This book was released on 1989 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: A corrosion and hydriding test series on zirconium alloys in the Engineering Test Reactor G-7 loop demonstrated relatively large lot-to-lot and alloy-to-alloy differences in hydriding rates under irradiation. Similar differences were also found among irradiated Zircaloy-2 pressure tubes fabricated by three suppliers for the Hanford Site N Reactor. This substantial in-reactor hydriding data base and access to archive materials from these same alloys permitted an investigation of methods to reproduce the in-reactor hydriding orders-of-merit by an out-of-reactor method.

Download or read book Zirconium in the Nuclear Industry written by Leo F. P. Van Swam and published by ASTM International. This book was released on 1989 with total page 781 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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.

Download or read book Official Gazette of the United States Patent and Trademark Office written by and published by . This book was released on 1990 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

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.

Download or read book Neutrographic Hydrogen Determination in Zirconium Alloys written by E. L. Esch and published by . This book was released on 1969 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: In the course of post-irradiation examinations of Zircaloy-2 clad fuel rods, it was recognized that it might be possible to detect hydriding of the cladding by using neutron radiography. Experiments were performed by applying indirect transfer methods for neutron radiography since direct exposure with a photographic film would not be appropriate with highly radioactive specimens. After neutron irradiation, dysprosium indirect transfer screens were put in contact with X-ray film for approximately 24 h. The X-ray film negatives were analyzed with a densitometer. Neutron radiography was shown to be effective for detection of hydrogen in thin-walled Zircaloy-2 tubing to a lower limit of 500 to 700 ppm. Using a densitometer of 1 percent precision, a sensitivity of about ±400 ppm through the center of the tube and ±200 ppm through the wall of the tube at the 1000-ppm level was obtained. The neutrographic technique was also used to detect local concentrations of zirconium hydride in irradiated Zircaloy-2 fuel cladding which were not identifiable by other non-destructive means. The method, though not sensitive below 500 ppm hydrogen is, nevertheless, useful. Using neutron radiography, it is possible to determine whether chemical analyses give values representative of the hydrogen concentration in an entire fuel rod; the complete distribution of hydrogen in the cladding can be determined.

Download or read book Zirconium in the Nuclear Industry written by D. G. Franklin and published by ASTM International. This book was released on 1984 with total page 866 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Zirconium in the Nuclear Industry written by and published by ASTM International. This book was released on with total page 849 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Creep of Zirconium Alloys in Nuclear Reactors written by and published by ASTM International. This book was released on with total page 308 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Zirconium in Nuclear Applications written by Schemel JH. and published by ASTM International. This book was released on 1974 with total page 532 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Mechanical Properties of Irradiated Zirconium Zircaloy and Aluminum written by Richard E. Schreiber and published by . This book was released on 1961 with total page 112 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Nuclear Radiation on the Corrosion Hydriding and Oxide Properties of Six Zirconium Alloys written by A. B. Johnson and published by . This book was released on 1969 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of in-reactor corrosion tests was conducted in the G-7 loop of the Engineering Test Reactor (ETR) in pH 10 NH4OH at 270 to 280 C. Six zirconium alloys were exposed in as-etched and prefilmed (400 C steam) surface conditions. The six alloys were Zircaloy-2, Zircaloy-4, Zr-3Nb-1Sn, Zr-2.5Nb, Zr-1.2Cu-0.28Fe, and Zr-1.2Cr-0.08Fe. Exposures were 25, 37, 77, and 174 days in high-flux, low-flux, out-of-flux, and out-of-reactor environments. Results from the 174-day exposure are emphasized, but corrosion and hydriding data from the complete test series are compared.

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:

Download or read book A New Model to Predict the Oxidation Kinetics of Zirconium Alloys in a Pressurized Water Reactor written by D. Pêcheur and published by . This book was released on 2008 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt: The previous CEA corrosion code COCHISE provided satisfactory simulations of in-reactor corrosion of the fuel cladding when used in its validity range. In contrast, it could lead to hazardous predictions if applied out of this range due to the strongly linked parameters mainly based on the analysis of French pressurized water reactor (PWR) data. To predict the oxidation kinetics for new operating conditions or new materials, the CEA and EDF decided to develop a new model, named CORCY, which is based on a more phenomenological approach and uses separate parameters deduced from analytical experiments. The aim of this paper is to present the new model for Zircaloy-4 in PWR. The phenomenological approach is described. It is based on out- and in-pile data. Typically, since (1) the oxidation kinetics of zirconium alloys in autoclave are periodic, and (2) the oxide films formed in autoclave, in out-of-pile loop, and in-reactor all exhibit periodic lateral cracks with a period similar to the oxide thickness to transition, the oxidation kinetics in CORCY are characterized by a cyclic repetition of semi-parabolic law. Each model parameter is detailed. They are deduced separately from (a) oxidation tests performed in autoclave on fresh alloys to determine their kinetics; (b) oxidation tests performed in the out-of-pile corrosion loops Corail and Reggae to quantify the effects of thermo-hydraulic conditions; (c) data provided by Testing Material Reactors (OSIRIS and Halden reactor) during isothermal oxidation to determine the effects of irradiation; and (d) oxidation tests performed on pre-hydrided alloys to take into account the accelerated corrosion phase occurring, in reactor, for Zircaloy-4 at high burn-up. After describing both the phenomenological approach and the different model parameters, a comparison of measured and calculated corrosion data from French PWRs at a burn-up up to 65 GWd/tU is provided.

Download or read book Method for Gas hydriding Zirconium Alloys at 400C written by J. Winton and published by . This book was released on 1966 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Creep of Zirconium Alloys in Nuclear Reactors written by D. G. Franklin and published by ASTM International. This book was released on 1983 with total page 322 pages. Available in PDF, EPUB and Kindle. Book excerpt: