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An Evaluation Of The Properties And Behavior Of Zirconium Uranium Alloys
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Book Synopsis ˜Anœ Evaluation of the properties and behavior of zirconium-uranium alloys by :
Download or read book ˜Anœ Evaluation of the properties and behavior of zirconium-uranium alloys written by and published by . This book was released on 1959 with total page 115 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis An Evaluation of the Properties and Behavior of Zirconium-uranium Alloys by : Arthur A. Bauer
Download or read book An Evaluation of the Properties and Behavior of Zirconium-uranium Alloys written by Arthur A. Bauer and published by . This book was released on 1959 with total page 124 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Comprehensive Investigation of the Uranium-Zirconium Alloy System by : Sangjoon Ahn
Download or read book Comprehensive Investigation of the Uranium-Zirconium Alloy System written by Sangjoon Ahn and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Uranium-zirconium (U-Zr) alloys comprise a class of metallic nuclear fuel that is regularly considered for application in fast nuclear energy systems. The U-10wt%Zr alloy has been demonstrated to very high burnup without cladding breach in the Experimental Breeder Reactor-II (EBR-II). This was accomplished by successfully accommodating gaseous fission products with low smear density fuel and an enlarged cladding plenum. Fission gas swelling behavior of the fuel has been experimentally revealed to be significantly affected by the temperature gradient within a fuel pin and the multiple phase morphologies that exist across the fuel pin. However, the phase effects on swelling behavior have not been yet fully accounted for in existing fuel performance models which tend to assume the fuel exists as a homogeneous single phase medium across the entire fuel pin. Phase effects on gas bubble nucleation and growth in the alloy were investigated using transmission electron microscopy (TEM). To achieve this end, a comprehensive examination of the alloy system was carried out. This included the fabrication of uranium alloys containing 0.1, 2, 5, 10, 20, 30, 40, and 50 wt% zirconium by melt-casting. These alloys were characterized using electron probe micro-analysis (EPMA), differential scanning calorimetry (DSC), and thermogravimetric analysis (TGA). Once the alloys were satisfactorily characterized, selected U-Zr alloys were irradiated with 140 keV He+ ions at fluences ranging from 1 X 1014 to 5 X 1016 ions/cm2. Metallographic and micro-chemical analysis of the alloys indicated that annealing at 600 °C equilibrates the alloys within 168 h to have stable [alpha]-U and [delta]-UZr2 phase morphologies. This was in contrast to some reported data that showed kinetically sluggish [delta]-UZr2 phase formation. Phase transformation temperatures and enthalpies were measured using DSC-TGA for each of the alloys. Measured temperatures from different time annealed alloys have shown consistent matches with most of the features in the current U-Zr phase diagram which further augmented the EPMA observed microstructural equilibrium. Nevertheless, quantitative transformation enthalpy analysis also suggests potential errors in the existing U-Zr binary phase diagram. More specifically, the ([Beta]-U, [gamma]2) phase region does not appear to be present in Zr-rich (> 15 wt%) U-Zr alloys and so further investigation may be required. To prepare TEM specimens, characterized U-Zr alloys were mechanically thinned to a thickness of ~150 [mu]m, and then electropolished using a 5% perchloric acid/95% methanol electrolyte. Uranium-rich phase was preferentially thinned in two phase alloys, giving saw-tooth shaped perforated boundaries; the alloy images were very clear and alloy characterization was accomplished. During in-situ heating U-10Zr and U-20Zr alloys up to 810 °C, selected area diffraction (SAD) patterns were observed as the structure evolved up to ~690 °C and the expected [alpha] --> [Beta]-U phase transformation at 662 °C was never observed. For the temperature range of the ([alpha]-U, [gamma]2) phase region, phase transformation driven diffusion was observed as uranium moved into Zr-rich phase matrix in U-20Zr alloy; this was noted as nonuniform bridging of adjacent phase lamellae in the alloy. From the irradiation tests, nano-scale voids were discovered to be evenly distributed over several micrometers in U-40Zr alloys. For the alloys irradiated at the fluences of 1 X 1016 and 5 X 1016 ions/cm2, estimated void densities were proportional to the irradiation doses, (250 ± 40) and (1460 ± 30) /[mu]m2, while void sizes were fairly constant, (6.0 ± 1.5) and (5.2 ± 1.2) nm, respectively. Measured data could be foundational inputs to the further development of a semi-empirical metal fuel performance model. The electronic version of this dissertation is accessible from http://hdl.handle.net/1969.1/151201
Book Synopsis AN EVALUATION OF DATA ON ZIRCONIUM-URANIUM ALLOYS. by :
Download or read book AN EVALUATION OF DATA ON ZIRCONIUM-URANIUM ALLOYS. written by and published by . This book was released on 1955 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Examination and Properties of Uranium Alloys by : Henry A. Saller
Download or read book Examination and Properties of Uranium Alloys written by Henry A. Saller and published by . This book was released on 1953 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis High-temperature Water and Steam-corrosion Behavior of Zirconium-uranium Alloys by : Stanley Kass
Download or read book High-temperature Water and Steam-corrosion Behavior of Zirconium-uranium Alloys written by Stanley Kass and published by . This book was released on 1959 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Tensile-creep Properties at 500 F of Zirconium and a 3.66 Per Cent Uranium Alloy of Zirconium by : A. D. Schwope
Download or read book Tensile-creep Properties at 500 F of Zirconium and a 3.66 Per Cent Uranium Alloy of Zirconium written by A. D. Schwope and published by . This book was released on 1952 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis High-Temperature Water and Steam-Corrosion Behavior of Zirconium-Uranium Alloys by :
Download or read book High-Temperature Water and Steam-Corrosion Behavior of Zirconium-Uranium Alloys written by and published by . This book was released on 1959 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Weight change vs. time curves expressing the corrosion behavior of zirconium alloys containing additions of 10 through 60 wt.% uranium tested in 600 and 680 F water and in 750 F steam at 1500 psi are presented. The effects of various heat treatments on the subsequent corrosion properties are also included. (auth).
Book Synopsis The Transformation Kinetics of Uranium-zirconium Alloys Containing 50 and 60 WT PCT Uranium by : John J. Kearns
Download or read book The Transformation Kinetics of Uranium-zirconium Alloys Containing 50 and 60 WT PCT Uranium written by John J. Kearns and published by . This book was released on 1956 with total page 40 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 1975-04 with total page 1082 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A Study of the Explosive Properties of Uranium-zirconium Alloys by : Robert P. Larsen
Download or read book A Study of the Explosive Properties of Uranium-zirconium Alloys written by Robert P. Larsen and published by . This book was released on 1954 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt: The prevention of explosions during pickling, etching or dissolution of these alloys has been studied; recommendations are made for safe handling. An unclassified safety film on this subject is available for distribution to interested laboratories.
Book Synopsis The Corrosion Properties of Zirconium-base Fuel Alloys by : Sam Kass
Download or read book The Corrosion Properties of Zirconium-base Fuel Alloys written by Sam Kass and published by . This book was released on 1956 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Physical Properties of Zirconium and Zirconium-Uranium Alloys by :
Download or read book Physical Properties of Zirconium and Zirconium-Uranium Alloys written by and published by . This book was released on 1951 with total page 29 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Development of Niobium-uranium Alloys for Elevated-temperature Fuel Applications by : John A. DeMastry
Download or read book Development of Niobium-uranium Alloys for Elevated-temperature Fuel Applications written by John A. DeMastry and published by . This book was released on 1961 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt: As a continuation of studies reported in BMI-1400, fabrication characteristics, physical and mechanical properties, and corrosion behavior in NaK, sodium, and water of niobium--uranium binary alloys containing up to 60 wt.% uranium were investigated. Alloys were cast by a skull melting and consumable and nonconsumable arc-melting methods. Fabrication difficulties with alloys containing greater than 25 wt.% uranium were related to coring-type microsegregation during casting. Tensile tests indicated 0.2% offset yield strengths of 16,880, 22,370 and 28,600 psi for niobium2000 deg F. Additional tensile data were obtained for alloys from 1600 to 2400 deg F. Stresses to produce minimum creep rates of 0.001, 0.01, and 0.1%/hr at 1600, 1800, and 2000 deg F were also determined. Both tensile and creep strengths were found to be sensitive to oxygen content. All alloys appeared compatible with NaK at 1600 deg F and with sodium at 1500 deg F. In 600 deg F water, most of the alloys tested exhibited negligible weight changes after 336 days' exposure. Weight changes were greater after 140 days' exposure to 680 deg F water, but corrosion rates were considered satisfactory for a clad fuel. The thermal and electrical conductivities of niobium are lowered by the addition of uranium, while the thermal-expansion characteristics are essentially unaffected. Recrystallization temperatures for 90% cold-reduced niobium-4.38, -14.3, -20, -25.0, and -30 wt.% uranium alloys are 2300, 2300, 2400, 2300, and 2200 deg F, respectively. No appreciable effect of oxygen contents ranging from 100 to 1000 ppm was observed on the composition limits of the gamma immiscibility gap in the niobium-- uranium system. (auth).
Book Synopsis The Determination of Uranium in Zirconium-uranium Alloys by : Clara Gale Goldbeck
Download or read book The Determination of Uranium in Zirconium-uranium Alloys written by Clara Gale Goldbeck and published by . This book was released on 1950 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Core Materials written by and published by . This book was released on 1958 with total page 812 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Proceedings of the USAEC Symposium on Zirconium Alloy Development, Castlewood, Pleasanton, California, November 12-14, 1962 by :
Download or read book Proceedings of the USAEC Symposium on Zirconium Alloy Development, Castlewood, Pleasanton, California, November 12-14, 1962 written by and published by . This book was released on 1962 with total page 428 pages. Available in PDF, EPUB and Kindle. Book excerpt: