Download or read book The Effect of Neutron Irradiation on the Mechanical Properties of Hydrided Zirconium Alloys written by Atomic Energy of Canada Limited and published by . This book was released on 1964 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Effect of Neutron Irradiation on the Mechanical Properties of Zirconium Alloy Fuel Cladding in Uniaxial and Biaxial Tests written by DG. Hardy and published by . This book was released on 1970 with total page 43 pages. Available in PDF, EPUB and Kindle. Book excerpt: Short-time axial tension, transverse ring tension, and biaxial closed end burst tests were conducted on sections of fuel cladding from 17 different batches and heat treatments of Zircaloy 2, Zircaloy 4, and Zr-2.5Cb alloy. Specimens were irradiated at 2 to 3x1020 n/cm2, E > x MeV, at temperatures of 125 to 250 C and tested at temperatures of 20 and 300 C.
Download or read book Report on the Effects of Neutron Radiation on Structural Materials written by M. Kangilaski and published by . This book was released on 1967 with total page 264 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 The effect of neutron irradiation on the mechanical properties of zirconium alloy fuel cladding in uniaxial and biaxial tests written by D. G. Hardy and published by . This book was released on 1971 with total page 0 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 The Effect of Irradiation on the Mechanical Properties of Arc melted Bureau of Mines Zirconium with Various Degrees of Cold Work written by R. S. Kemper and published by . This book was released on 1955 with total page 68 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Influence of Neutron Irradiation on the Mechanical Properties and the Corrosion Behaviour of ZrNb3Sn1 and Zircaloy 2 written by H. Richter and published by . This book was released on 1967 with total page 31 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The effect of neutron irradiation on the mechanical properties of zirconium fuel cladding alloys in uniaxial and biaxial tests written by D. G. Hardy and published by . This book was released on 1970 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Hydrogen Trapping at Neutron Irradiation Produced Defects in Recrystallized Alpha Annealed Zircaloy 4 written by Bruce F. Kammenzind and published by . This book was released on 2018 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt: Hydrogen is absorbed into zirconium alloy-clad fuel elements and structural components as a result of water-side corrosion in both pressurized water reactor (PWR) and boiling water reactor (BWR) environments. Increasing hydrogen concentrations in the zirconium alloy affect both its mechanical properties and dimensional stability. It is well known that hydrogen can diffuse relatively rapidly through zirconium base alloys (in relation to the lifetime of the components) in response to solid solution concentration, temperature, and stress gradients. Migration of hydrogen within a component through its life must be considered to reliably predict the performance of the component through life and even post-service life. Many of the physical properties needed to describe this process, such as the solubility of hydrogen in zirconium alloys, diffusion coefficients of hydrogen through zirconium alloys, and the Soret effect within zirconium alloys, already have been published. Many of these measurements have been made outside of the reactor core environment on nonirradiated zirconium alloys.
Download or read book The Effect of Neutron Irradiation on the Mechanical Properties of Metals written by M. J. Makin and published by . This book was released on 1956 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Irradiation Effects on Structural Alloys for Nuclear Reactor Applications written by A. L. Bement and published by ASTM International. This book was released on 1971 with total page 571 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Effects of Neutron Irradiation on the Elevated Temperature Mechanical Properties of Nickel Base and Refractory Metal Alloys written by T. T. Claudson and published by . This book was released on 1967 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear research and power reactors are now being designed which must operate at temperatures and coolant environments dictating the use of nickel-base and refractory metal alloys for structural components, fuel cladding, and power equipment. Investigation of the effects of irradiation and environment upon the mechanical properties of several nickel-base and refractory metal alloys has been initiated at the Pacific Northwest Laboratory. Tension specimens of Inconel 600, Inconel 625, Inconel 702, Inconel 718, Incoloy 800, Hastelloy C, Hastelloy N, Hastelloy X-280, and Hastelloy R-235 have been irradiated to exposures exceeding 1 x 1021 nvt (E > 1 Mev) in 50 C water, 280 C water, and 740 C gaseous environments. These specimens have been tested in the pre- and postirradiated conditions at room temperature, 300 C, and 650 C. Several metallurgical conditions of the materials have also been examined and the changes in mechanical properties due to the irradiation have been noted. The Cb-1 Zr, Cb-752, TZM Mo, and W-25 Re refractory metals have been irradiated at ambient temperatures, and the effects of irradiation upon the mechanical properties have been evaluated at room temperature and 1090 C. The data obtained for both the nickel-base and refractory metal alloys tested indicate that there is a marked effect upon the mechanical properties due to the thermal environment. In addition to this effect, effects due to the irradiation were also found. Comparison of the elevated temperature data to the room temperature data shows a marked decrease in both strength and ductility. Metallographic examination of these materials is continuing in an attempt to find the cause of these damages.
Download or read book Zirconium in Nuclear Applications written by J. H. Schemel and published by ASTM International. This book was released on 1974 with total page 544 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Effect of Neutron Irradiation on the Mechanical Properties of Zirconium 2 5 Percent Niobium Alloy written by Atomic Energy of Canada Limited and published by . This book was released on 1960 with total page 35 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Effect of Neutron Irradiation Hydride Precipitate and Hydride Layers on the Impact Properties of Zircaloy 2 written by L. M. Howe and published by . This book was released on 1961 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Effects of Cold Work and Neutron Irradiation on the Tensile Properties of Zircaloy 2 written by Arden Lee Bement (Jr.) and published by . This book was released on 1963 with total page 214 pages. Available in PDF, EPUB and Kindle. Book excerpt:
