In-pile Loop Investigations of Corrosion of Zircaloy-2 and Other Possible Reactor Materials in 0.04 M UO2SO4 at 280°C PDF Download
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Author: Glenn Herbert Jenks
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 52
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Author: Glenn Herbert Jenks
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 52
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Author:
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 44
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Author: United States. Department of Commerce. Office of Technical Services
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 522
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Author: Frederic R. Shober
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ISBN:
Category : Metals
Languages : en
Pages : 120
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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).
Author: Glenn Herbert Jenks
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ISBN:
Category : Irradiation
Languages : en
Pages : 50
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Author:
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ISBN:
Category : Corrosion and anti-corrosives
Languages : en
Pages : 638
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Author: Defense Metals Information Center
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ISBN:
Category : Metallurgy
Languages : en
Pages : 914
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Author: Battelle Memorial Institute. Radiation Effects Information Center
Publisher:
ISBN:
Category :
Languages : en
Pages : 120
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Author: G. H. Jenks
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ISBN:
Category : Zirconium alloys
Languages : en
Pages : 17
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A correlation and analysis of many of the data obtained at Oak Ridge National Laboratory (ORNL) for the in-pile corrosion of Zircaloy-2 in oxygenated uranyl sulfate solutions is described. These data were obtained in a program of in-pile loop and autoclave experiments in which a variety of solution compositions, solution velocities, fission power densities, and temperatures were tested. The experiments had the objective of obtaining information which would enable the prediction and control of corrosion in homogeneous reactors. The correlations were based on the following equation for the relationship between corrosion rate, R (mil per year), and fission power density in solution, P(w per ml), 1/R = K1/KP? + 1/K, where ? is a factor by which the effective power density at a corroding surface is greater than that in solution, owing to uranium sorption on the surface; K1 and K are other factors evaluated from the data. A semi-empirical model for the radiation effects on the corrosion which leads to this equation is described. A brief review of experimental methods and results is also given. Considerations of the experimental corrosion data at 280 C and of probable relative and absolute values of ? led to the conclusions that a relationship of the above form was obeyed up to the highest power density tested (110 w per ml), and that the values of K and K1/K were essentially independent of changes in solution composition. On the bases of the reasonable assumptions that the general relationship, with K and K1/K independent of solution composition, was obeyed at other temperatures, and that the values of ? in certain experiments did not change appreciably with change in temperature, it was concluded that over the temperature range investigated (225 to 330 C) the data obtained in all experiments were reasonably well represented by the equation: 1/R=2.3P?+2.3x10-11exp(11,500T). The value of ? is dependent upon solution composition and velocity, and values ranging from unity to about 14 were observed. Conditions under which values of ? near unity can be maintained in a reactor can be estimated from the results of this work.
Author: British Nuclear Energy Society
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 480
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