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.
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:
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.
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 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 Studies of Zirconium Alloy Corrosion and Hydrogen Uptake During Irradiation written by VF. Urbanic and published by . This book was released on 2000 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: The in-reactor corrosion and hydrogen pickup of Zircaloy-2 and Zr-2.5Nb pressure tube materials are being studied in two test loops: a light water loop in the NRU research reactor, and a new heavy water loop in the Halden reactor. The complimentary test programs examine the corrosion behavior of small specimens as a function of fast neutron flux and fluence, temperature, water chemistry, and specimen pre-oxidation.
Download or read book Corrosion of Zirconium Alloys in 900 Steam written by J. Paul Pemsler and published by . This book was released on 1958 with total page 26 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 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 The Oxidation and Corrosion of Zirconium and Its Alloys written by Atomic Energy Research Establishment (Harwell, England) and published by . This book was released on 1959 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Corrosion Testing of Zircaloy 2 and Zircaloy 3 written by Stanley Kass and published by . This book was released on 1957 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Oxidation and Corrosion of Zirconium and Its Alloys written by Atomic Energy Research Establishment (Harwell, England) and published by . This book was released on 1959 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 In pile autoclave Test of Zircaloy 2 Corrosion in UO2 NO3 2 Solution and of Solution Stability written by R. J. Davis and published by . This book was released on 1962 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Neutron Irradiation and Cold Work Effects on Zircaloy 2 Corrosion and Hydrogen Pickup written by H. P. Maffei and published by . This book was released on 1964 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nearly 200 pre-autoclaved and weighed coupons of reactor-grade Zircaloy-2 in the annealed, 10, 20, and 40 per cent cold-worked condition have been exposed to the fast neutron flux of the Engineering Test Reactor (ETR) in nominal 540 F pH 10 water for up to 125 days. Flux intensity varied from 0.17 to 1.04 x 1014 nv (>1 Mev), and integrated neutron exposures ranged from 0.3 to 8.2 x 1020 nvt. Comparisons of weight gain and hydrogen pickup results among irradiated specimens and with unirradiated control coupons were used to broaden the area of present knowledge relative to the combined effects of neutron irradiation and cold work on surface chemical reactions and hydrogen absorption in Zircaloy-2. In general, exposure to the in-core coolant environment of the ETR causes an order-of-magnitude increase in average corrosion rates, similar to the effect of superheated steam at a temperature approximately 200 F above the irradiation temperature. In-reactor weight-gain data exhibit an apparent saturation effect with increasing flux intensity, and measured weight gains have been confirmed by optical measurements of oxide film thickness. Direct visual observations and photography at magnifications up to 40 x of irradiated coupons oxidized to weight gains as high as 150 mg/dm2 showed the surfaces to be smooth, glossy, and dark gray or blue-black in color. Some of the coupons appeared to be streak stained, but there were no indications of blistering, spalling, or light-colored oxide even at sharp edges and corners. No significant or consistent variation of weight gain with cold work has been found for material exposed in- or out-of-reactor. No significant effect of flux intensity or integrated flux on hydrogen sorption was observed.
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 Corrosion of Zircaloy Base Fuel Alloys in High Temperature Water written by Stanley Kass and published by . This book was released on 1958 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:
