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Book A positron annihilation study of defect recovery in electron irradiated alpha zr

Download or read book A positron annihilation study of defect recovery in electron irradiated alpha zr written by G. M. Hood and published by . This book was released on 1977 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book A positron annihilation spectroscopy study of electron irradiation damage recovery in zr 2 5nb and in the very low fe alloys zr 2 5 nb zr 19 nb and zr 19 nb 1 fe

Download or read book A positron annihilation spectroscopy study of electron irradiation damage recovery in zr 2 5nb and in the very low fe alloys zr 2 5 nb zr 19 nb and zr 19 nb 1 fe written by G. M. Hood and published by . This book was released on 1996 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The recovery of single crystal alpha zr from low temperature electron irradiation a positron annihilation spectroscopy study

Download or read book The recovery of single crystal alpha zr from low temperature electron irradiation a positron annihilation spectroscopy study written by G. M. Hood and published by . This book was released on 1984 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Corrosion of Electron Irradiated Zr 2 5Nb and Zircaloy 2

Download or read book Corrosion of Electron Irradiated Zr 2 5Nb and Zircaloy 2 written by OT. Woo and published by . This book was released on 2000 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt: We used 10-MeV electrons to rapidly produce radiation damage in zirconium alloys, investigated whether electrons produced the same microstructural changes as neutrons, then performed post-irradiation corrosion tests to determine whether electron-irradiated materials displayed similar corrosion behavior to neutron-irradiated materials.

Book Corrosion of electron irradiated zr 2 5nb and zircaloy 2

Download or read book Corrosion of electron irradiated zr 2 5nb and zircaloy 2 written by O. T. Woo and published by . This book was released on 2000 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Effect of Iron on Dislocation Evolution in Model and Commercial Zirconium Alloys

Download or read book The Effect of Iron on Dislocation Evolution in Model and Commercial Zirconium Alloys written by Matthew Topping and published by . This book was released on 2018 with total page 27 pages. Available in PDF, EPUB and Kindle. Book excerpt: Although the evolution of irradiation-induced dislocation loops has been well correlated with irradiation-induced growth phenomena, the effect of alloying elements on this evolution remains elusive, especially at low fluences. To develop a more mechanistic understanding of the role iron has on loop formation, we used state-of-the-art techniques to study a proton-irradiated Zr-0.1Fe alloy and proton- and neutron-irradiated Zircaloy-2. The two alloys were irradiated with 2-MeV protons up to 7 dpa at 350°C and Zircaloy-2 up to 14.7 x 1025 n . m-2, approximately 24 dpa, in a boiling water reactor at approximately 300°C. Baseline transmission electron microscopy showed that the Zr3Fe secondary-phase particles in the binary system were larger and fewer in number than the Zr(Fe,Cr)2 and Zr2(Fe,Ni) particles in Zircaloy-2. An analysis of the irradiated binary alloy revealed only limited dissolution of Ze3Fe, suggesting little dispersion of iron into the matrix, while at the same time a higher a-loop density was observed compared with Zircaloy-2 at equivalent proton dose levels. We also found that the redistribution of iron during irradiation led to the formation of iron nanoclusters. A delay in the onset of c-loop nucleation in proton-irradiated Zircaloy-2 compared with the binary alloy was observed. The effect of iron redistributed from secondary-phase particles because of dissolution on the density and morphology of a and c loops is described. The implication this may have on irradiation-induced growth of zirconium fuel cladding is also discussed.

Book Recovery and Recrystallization of Zirconium and Its Alloys

Download or read book Recovery and Recrystallization of Zirconium and Its Alloys written by Spencer Harrison Bush and published by . This book was released on 1961 with total page 134 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Irradiation Effects on Fe Distributions in Zircaloy 2 and Zr 2 5Nb

Download or read book Irradiation Effects on Fe Distributions in Zircaloy 2 and Zr 2 5Nb written by Chalk River Nuclear Laboratories. Reactor Materials Research Branch and published by Chalk River, Ont. : Reactor Materials Research Branch, Chalk River Laboratories. This book was released on 1995 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Impact of Irradiation Damage Recovery During Transportation on the Subsequent Room Temperature Tensile Behavior of Irradiated Zirconium Alloys

Download or read book Impact of Irradiation Damage Recovery During Transportation on the Subsequent Room Temperature Tensile Behavior of Irradiated Zirconium Alloys written by B. Bourdiliau and published by . This book was released on 2010 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt: Zirconium alloys are commonly used in pressurized water reactor as fuel rod cladding tubes. After irradiation and cooling in pool, the spent nuclear fuel assemblies are either transported for wet storage to a devoted site or loaded in suitable casks for dry storage on a nuclear power plant site. During dry transportation or at the beginning of dry storage, at temperatures around 400°C, the cladding experiences a creep deformation under the hoop stress induced by the internal pressure of the fuel rod. During creep, a recovery of the radiation damage can occur that can affect the subsequent mechanical properties. The mechanical behavior of the cladding has been investigated in laboratory on two neutron irradiated cladding materials: fully recrystallized Zr-1 % Nb and stress-relieved Zircaloy-4. Creep tests under internal pressure were conducted at 400 and 420°C. After depressurization and cooling, ring tensile tests were carried out at room temperature. In addition, transmission electron microscopy observations have been performed after testing. The post-creep mechanical response exhibited a decrease of the strength compared to the as-irradiated material. This decrease is associated with a significant recovery of the ductility, which becomes close to the ductility of the unirradiated material. The transmission electron microscopy examinations, conducted on recrystallized Zr-1 % Nb ring samples, revealed that the radiation defects have been annealed. It was also observed that as for the unirradiated material, the deformation occurred homogeneously throughout the grains. No dislocation channeling was observed contrary to the as-irradiated material. These observations explain the recovery of the strength and of the ductility after post-irradiation creep that may also occur during dry transportation or at the beginning of dry storage.

Book Positron Lifetime and Doppler Broadening Techniques Applied to Irradiation damaged Silver

Download or read book Positron Lifetime and Doppler Broadening Techniques Applied to Irradiation damaged Silver written by and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Positron lifetime and Doppler broadening measurements have been used to study defect production resulting from room temperature irradiation of pure silver by D-T fusion neutrons or energetic protons. Use of the positron annihilation analysis has established that the surviving defects from both irradiations have the same dose dependence and that defect concentration can be quantitatively measured and compared to damage models. The relative merit of the lifetime and Doppler broadening measurements in arriving at these conclusions is discussed in this report along with some practical aspects of the measurements. In the proton damaged samples the trapping rate approaches saturation, a circumstance which could be misinterpreted if a less extensive data set containing only Doppler broadening data were available. Some remarks about the analysis of positron data and general conclusions about the defect structure are given. 3 figures.

Book Investigation of Variables That Influence Corrosion of Zirconium Alloys During Irradiation

Download or read book Investigation of Variables That Influence Corrosion of Zirconium Alloys During Irradiation written by VF. Urbanic and published by . This book was released on 1991 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: The in-reactor corrosion of Zircaloy-2 and Zr-2.5Nb pressure tube materials is being studied by exposing small specimens in water-cooled loops in the NRU research reactor. Experiments are designed to investigate the effects of fast-neutron irradiation, water chemistry, temperature, and pre-oxidation on the corrosion behaviour. Preliminary results show that inreactor corrosion rates of both alloys increase with increasing concentrations of dissolved oxygen in the water. In the absence of irradiation, only Zr-2.5Nb is sensitive to its presence. Excursions to oxidizing (?300 (?g/kg oxygen) water chemistry in nominally low oxygen tests are seen to induce high oxidation rates for both Zircaloy-2 and Zr-2.5Nb during irradiation. The consequences of oxygen excursions are less pronounced on material prefilmed in 673 K steam. The oxides formed in different chemistry regimes are characterized using scanning electron microscopy and capacitance techniques.

Book Use of Ion Bombardment to Study Irradiation Damage in Zirconium Alloys

Download or read book Use of Ion Bombardment to Study Irradiation Damage in Zirconium Alloys written by RB. Adamson and published by . This book was released on 1974 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: Zircaloy-2 having several different microstructures, textures, and compositions has been bombarded with either 5 MeV or 46.5 MeV nickel ions at 300 to 600°C to achieve doses ranging from 0.65 to 87.0 displacements per atom (dpa). Similar material was reactor-irradiated near 320°C to neutron fluences between 0.8 and 3.2dpa. Transmission electron microscopy methods were used to identify and compare the nature of the defect structure produced by the ions and neutrons.