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Book Scientific and Technical Aerospace Reports

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1967 with total page 348 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Science Abstracts

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1964-04 with total page 1622 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Effect of Nuclear Radiation on Structural Metals

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).

Book The Effect of Neutron Irradiation on the Mechanical Properties of Welded Zircaloy 2

Download or read book The Effect of Neutron Irradiation on the Mechanical Properties of Welded Zircaloy 2 written by D. G. Evans and published by . This book was released on 1962 with total page 23 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Mechanical Properties of Irradiated Zirconium Zircaloy and Aluminum

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:

Book Neutron Irradiation and Cold Work Effects on Zircaloy 2 Corrosion and Hydrogen Pickup

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.

Book The Effect of Neutron Irradiation on the Mechanical Properties of Zirconium Alloy Fuel Cladding in Uniaxial and Biaxial Tests

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.

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 The Effect of Neutron Irradiation on the Tensile Properties of Zircaloy 2

Download or read book The Effect of Neutron Irradiation on the Tensile Properties of Zircaloy 2 written by L. M. Howe and published by . This book was released on 1959 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Effect of Neutron Irradiation and Cold Work on the Strain Aging Behavior of Zircaloy 2

Download or read book The Effect of Neutron Irradiation and Cold Work on the Strain Aging Behavior of Zircaloy 2 written by W. B. Rotsey and published by . This book was released on 1969 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: The strain-aging behavior of annealed Zircaloy-2 in vacuum was studied as a function of deformation temperature, integrated fast-neutron dose, and degree of cold work. Strain aging occurred in the temperature range 200 to 500 C. Transmission electron microscopy showed that in the temperature range 300 to 450 C, dislocations were arranged in a cell structure, and that at 500 C two-dimensional hexagonal dislocation nets were present. Between 200 and 400 C, the strain aging was found to be due to the presence of oxygen; however, the origin of the strain aging between 400 and 500 C was not identified.

Book Effect of Corrosion and Fast Neutron Irradiation on the Mechanical Properties of the Zirconium 8 6 Wt Aluminium Reference Material

Download or read book Effect of Corrosion and Fast Neutron Irradiation on the Mechanical Properties of the Zirconium 8 6 Wt Aluminium Reference Material written by Atomic Energy of Canada Limited and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: