Download or read book Effect of Radiation on the Corrosion of Zircaloy 2 written by and published by . This book was released on 1957 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Review and Correlation of In pile Zircaloy 2 Corrosion Data and a Model for the Effect of Irradiation written by Glenn Herbert Jenks and published by . This book was released on 1961 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effect of Surface Treatment on the Irradiation Enhancement of Corrosion of Zircaloy 2 in HBWR written by L. Lunde and published by . This book was released on 1974 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Specimens of Zircaloy-2 have been exposed at 240°C (464°F) in various locations in the primary circuit of the Halden Boiling Water Reactor (HBWR). Corrosion data have also been collected from Zircaloy-2 clad fuel elements. The radiation field caused a drastic enhancement of the attack, corrosion rates increased a hundred times, and was under normal conditions about 0.15 mg/dm2 per day for pickled, anodized, and autoclaved material. Variations in the flux level from 2 x 109 to 3 x 1012 neutrons (n)/cm2 . s (> 1 MeV) had little influence on the corrosion rate, and it is suggested that ?-irradiation or lower energy neutrons, rather than fast neutrons, can be responsible for the corrosion enhancement. When uranium was present in the water, the corrosion rate increased for pickled and for autoclaved fuel rods, while hardly any effect was observed with anodized material. A deliberate fluoride contamination on the specimens increased the corrosion rate in-pile as well as out-of-pile. By anodizing this harmful effect of fluorides could be completely counteracted.

Download or read book The effect of radiation on the aqueous corrosion of zircaloy written by R. C. Asher and published by . This book was released on 1973 with total page 102 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Effect of Nuclear Radiation on Metallic Fuel Materials written by A. A. Bauėr and published by . This book was released on 1963 with total page 150 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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:

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976-02 with total page 722 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Effect of Nuclear Radiation on Structural Metals written by Frederic R. Shober and published by . This book was released on 1961 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effect of fast-neutron (>1 Mev) irradiation on the mechanical properties of structural metals and alloys was studied. Although the yield strengths and ultimate tensile strengths are increased su stantially for most materials, the ductility suffers severe decreases. This report presents these changes in properties of several structural metals for a number of neutron exposures within the 1.0 x 10 to the 18th power to 5.0 x 10 to the 21st power n/sq cm range. Data summarizing these effects on several classes of materials such as carbon steels, low-alloy steels, stainless steels, Zr-base alloys, ni-base alloys, Al-base alloys, and Ta are given. Additional data which show the influence f irradiation temperatures and of post-irradiation annealing on the radiation-induced property changes are also given and discussed. Increases as great as 175% in yield strength, 100% in ultimate strength, and decreases of 80% in total elongation are reported for fast-neutron exposures as great as 5 10 to the 21st power n/sq cm. (Author).

Download or read book Effects of Radiation on Materials written by Roger E. Stoller and published by ASTM International. This book was released on 1992 with total page 1315 pages. Available in PDF, EPUB and Kindle. Book excerpt: Symposium held in Nashville, Tennessee, June 1990. Almost two-thirds of these 91 papers are authored by researchers outside of the US (including information on research in the former USSR, Japan, and Europe). Topics include: current commercial power reactor systems; microstructural characterization

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 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 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 The Role of Gamma Radiation on Zircaloy 4 Corrosion written by Douglas M. Rishel and published by . This book was released on 2018 with total page 41 pages. Available in PDF, EPUB and Kindle. Book excerpt: A key microstructural feature of irradiated oxide films that form on Zircaloy-4 is the development of significant amounts of interconnected porosity or microcracking, particularly along oxide grain boundaries. This development disrupts the protective nature of the barrier layer, effectively resulting in an increase in the observed post-transition corrosion rates. This observation suggests that some aspect of oxide dissolution may be occurring. It is noteworthy that when exposed to photons with energies greater than that of the oxide band gap, n-type semiconducting oxides are prone to dissolution. Because zirconia (ZrO2) is an n-type semiconductor, it is plausible that high-energy photons may play an important role in corrosion. In an operating nuclear reactor, neutron and gamma flux levels are closely interrelated because they arise, for the most part, from the same originating process (i.e., the fissioning of nuclear fuel). Thus, it is difficult to isolate the independent effects of neutron and gamma radiation on corrosion. It is, however, theoretically conceivable to assess the role that gamma radiation may have on corrosion by comparing instances where variations in radiation environment exists; specifically by comparing where variations in gamma flux levels relative to neutron flux levels within different regions of a reactor or from reactor to reactor exist. Comparisons of the corrosion rates obtained between two different reactors (the Halden test reactor and the advanced test reactor [ATR]) that have differing gamma-to-neutron ratios were performed. In addition, an examination of corrosion rate data from the ATR, in which a variation in gamma-to-neutron flux ratio exists, was also conducted. Results are presented, from both assessments, which indicate that gamma radiation plays a role in the irradiated corrosion behavior of Zircaloy-4. In addition to a discussion of experimental data, potential mechanisms associated with photon-induced oxide dissolution of n-type semiconducting oxides, such as zirconia, is also provided.

Download or read book Corrosion of Zirconium Alloys written by and published by . This book was released on 1964 with total page 156 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Zirconium in the Nuclear Industry written by George P. Sabol and published by ASTM International. This book was released on 1996 with total page 907 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Plasma Electrolytic Oxidation PEO Coatings written by Marta Mohedano and published by MDPI. This book was released on 2021-06-02 with total page 172 pages. Available in PDF, EPUB and Kindle. Book excerpt: Plasma electrolytic oxidation (PEO), also known as micro-arc oxidation (MAO), functionalizes surfaces, improving the mechanical, thermal, and corrosion performance of metallic substrates, along with other tailored properties (e.g., biocompatibility, catalysis, antibacterial response, self-lubrication, etc.). The extensive field of applications of this technique ranges from structural components, in particular, in the transport sector, to more advanced fields, such as bioengineering. The present Special Issue covers the latest advances in PEO‐coated light alloys for structural (Al, Mg) and biomedical applications (Ti, Mg), with 10 research papers and 1 review from leading research groups around the world.

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.