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X Ray And Tem Characterization Of The Uranium Zirconium Alloy Fuel For The Integral Fast Reactor
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Book Synopsis X-ray and TEM Characterization of the Uranium-zirconium Alloy Fuel for the Integral Fast Reactor by : Tracy Lynne Wonnell
Download or read book X-ray and TEM Characterization of the Uranium-zirconium Alloy Fuel for the Integral Fast Reactor written by Tracy Lynne Wonnell and published by . This book was released on 1988 with total page 112 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 Hot Extrusion of Alpha Phase Uranium-zirconium Alloys for Tru Burning Fast Reactors by : Jeffrey Stephen Hausaman
Download or read book Hot Extrusion of Alpha Phase Uranium-zirconium Alloys for Tru Burning Fast Reactors written by Jeffrey Stephen Hausaman and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The development of fast reactor systems capable of burning recycled transuranic (TRU) isotopes has been underway for decades at various levels of activity. These systems could significantly alleviate nuclear waste storage liabilities by consuming the long-lived isotopes of plutonium (Pu), neptunium (Np), americium (Am), and curium (Cm). The fabrication of metal fuel alloys by melt casting pins containing the volatile elements Am and Np has been a major challenge due to their low vapor pressures; initial trials demonstrated significant losses during the casting process. A low temperature hot extrusion process was explored as a potential method to fabricate uranium-zirconium fuel alloys containing the TRU isotopes. The advantage of extrusion is that metal powders may be mixed and enclosed in process canisters to produce the desired composition and contain volatile components. Uranium powder was produced for the extrusion process by utilizing a hydride-dehydride process that was developed in conjunction with uranium alloy sintering studies. The extrusions occurred at 600°C and utilized a hydraulic press capable of 450,000 N (50 tons) of force. Magnesium (Mg) metal was used as a surrogate metal for Pu and Am because of its low melting point (648°C) and relatively high vapor pressure (0.2 atm at 725°C). Samples containing U, Zr, and Mg powder were prepared in an inert atmosphere glovebox using copper canisters and extruded at 600°C. The successful products of the extrusion method were characterized using thermal analysis with a differential scanning calorimeter as well as image and x-ray analysis utilizing an electron microprobe. The analysis showed that upon fabrication the matrix of the extruded metal alloy is completely heterogeneous with no mixing of the metal particle constituents. Further heat treating upon this alloy allows these different materials to interdiffuse and form mixed uraniumz-irconium phases with varying types of microstructures. Image and x-ray analysis showed that the magnesium surrogate present in a sample was retained with little evidence of losses due to vaporization.
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:
Book Synopsis Scientific and Technical Aerospace Reports by :
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1972 with total page 248 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Powder Metallurgy of Uranium Alloy Fuels for TRU-Burning Reactors Final Technical Report by :
Download or read book Powder Metallurgy of Uranium Alloy Fuels for TRU-Burning Reactors Final Technical Report written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Interdiffusion Reaction Between Uranium-zirconium and Iron by : Young Joo Park
Download or read book Interdiffusion Reaction Between Uranium-zirconium and Iron written by Young Joo Park and published by . This book was released on 2013 with total page 51 pages. Available in PDF, EPUB and Kindle. Book excerpt: U-Zr metallic fuels cladded in Fe-alloys are being considered for application in an advanced Sodium-Cooled Fast Reactor (SFR) that can recycle the U-Zr fuels and minimize the long-lived actinide waste. To understand the complex fuel-cladding chemical interaction of the U-Zr metallic fuel with Fe-alloys, a systematic multicomponent diffusion study was carried out using solid-to-solid diffusion couples. The U-10 wt.% Zr vs. pure Fe diffusion couples were assembled and annealed at temperatures, 630, 650 and 680°C for 96 hours. Development of microstructure, phase constituents, and compositions developed during the thermal anneals were examined by scanning electron microscopy, transmission electron microscopy and X-ray energy dispersive spectroscopy. A complex microstructure consisting of several layers that include phases such as U6Fe, UFe2, ZrFe2, [alpha]-U, [beta]-U, Zr-precipitates, [chi], [epsilon], and [lambda] was observed. Multi-phase layers were grouped based on phase constituents and microstructure, and the layer thicknesses were measured to calculate the growth constant and activation energy. The local average compositions through the interaction layer were systematically determined, and employed to construct semi-quantitative diffusion paths on isothermal U-Zr-Fe ternary phase diagrams at respective temperatures. The diffusion paths were examined to qualitatively estimate the diffusional behavior of individual components and their interactions. Furthermore, selected area diffraction analyses were carried out to determine, for the first time, the exact crystal structure and composition of the [chi], [epsilon] and [lambda]-phases. The [chi], [epsilon] and [lambda]-phases were identified as Pnma(62) Fe(Zr, U), I4/mcm(140) Fe(Zr, U)2, and I4/mcm(140) U3(Zr, Fe), respectively.
Book Synopsis Progress Relating to Civilian Applications During ... by :
Download or read book Progress Relating to Civilian Applications During ... written by and published by . This book was released on 1957-11 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 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:
Book Synopsis Recent Irradiation Tests of Uranium-plutonium-zirconium Metal Fuel Elements by :
Download or read book Recent Irradiation Tests of Uranium-plutonium-zirconium Metal Fuel Elements written by and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Uranium-Plutonium-Zirconium metal fuel irradiation tests to support the ANL Integral Fast Reactor concept are discussed. Satisfactory performance has been demonstrated to 2.9 at.% peak burnup in three alloys having 0, 8, and 19 wt % plutonium. Fuel swelling measurements at low burnup in alloys to 26 wt % plutonium show that fuel deformation is primarily radial in direction. Increasing the plutonium content in the fuel diminishes the rate of fuel-cladding gap closure and axial fuel column growth. Chemical redistribution occurs by 2.1 at.% peak burnup and generally involves the inward migration of zirconium and outward migration of uranium. Fission gas release to the plenum ranges from 46% to 56% in the alloys irradiated to 2.9 at.% peak burnup. No evidence of deleterious fuel-cladding chemical or mechanical interaction was observed.
Book Synopsis Characterization of Alpha-phase Sintering of Uranium and Uranium-zirconium Alloys for Advanced Nuclear Fuel Applications by : Grant Helmreich
Download or read book Characterization of Alpha-phase Sintering of Uranium and Uranium-zirconium Alloys for Advanced Nuclear Fuel Applications written by Grant Helmreich and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The sintering behavior of uranium and uranium-zirconium alloys in the alpha phase were characterized in this research. Metal uranium powder was produced from pieces of depleted uranium metal acquired from the Y-12 plant via hydriding/dehydriding process. The size distribution and morphology of the uranium powder produced by this method were determined by digital optical microscopy. Once the characteristics of the source uranium powder were known, uranium and uranium-zirconium pellets were pressed using a dual-action punch and die. The majority of these pellets were sintered isothermally, first in the alpha phase near 650°C, then in the gamma phase near 800°C. In addition, a few pellets were sintered using more exotic temperature profiles. Pellet shrinkage was continuously measured in situ during sintering. The isothermal shrinkage rates and sintering temperatures for each pellet were fit to a simple model for the initial phase of sintering of spherical powders. The material specific constants required by this model, including the activation energy of the process, were determined for both uranium and uranium-zirconium. Following sintering, pellets were sectioned, mounted, and polished for imaging by electron microscopy. Based on these results, the porosity and microstructure of the sintered pellets were analyzed. The porosity of the uranium-zirconium pellets was consistently lower than that of the pure uranium pellets. In addition, some formation of an alloyed phase of uranium and zirconium was observed. The research presented within this thesis is a continuation of a previous project; however, this research has produced many new results not previously seen. In addition, a number of issues left unresolved by the previous project have been addressed and solved. Most notably, the low original output of the hydride/dehydride powder production system has been increased by an order of magnitude, the actual characteristics of the powder have been measured and determined, shrinkage data was successfully converted into a sintering model, an alloyed phase of uranium and zirconium was produced, and pellet cracking due to delamination has been eliminated.
Book Synopsis Characterization of Alpha-phase Sintering of Uranium and Uranium-zirconium Alloys for Advanced Nuclear Fuel Applications by : Grant William Helmreich
Download or read book Characterization of Alpha-phase Sintering of Uranium and Uranium-zirconium Alloys for Advanced Nuclear Fuel Applications written by Grant William Helmreich and published by . This book was released on 2010 with total page 105 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 Development and Properties of Coextruded Zircaloy-clad Uranium Fuel Elements with Integral End Seals by : H. F. Sawyer
Download or read book Development and Properties of Coextruded Zircaloy-clad Uranium Fuel Elements with Integral End Seals written by H. F. Sawyer and published by . This book was released on 1958 with total page 82 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Creep of Zirconium Alloys in Nuclear Reactors by :
Download or read book Creep of Zirconium Alloys in Nuclear Reactors written by and published by ASTM International. This book was released on with total page 308 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Specific Zirconium Alloy Design Program Quarterly Progress Report by :
Download or read book Specific Zirconium Alloy Design Program Quarterly Progress Report written by and published by . This book was released on 1962-02 with total page 128 pages. Available in PDF, EPUB and Kindle. Book excerpt:
