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Thermal Conductivities Of U3si And U3si2 Al Dispersion Fuels
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Book Synopsis Thermal Conductivities of U3Si and U3Si2-Al Dispersion Fuels by :
Download or read book Thermal Conductivities of U3Si and U3Si2-Al Dispersion Fuels written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Two high density uranium silicides are being evaluated as replacements for the research reactor fuels currently in use. Employing these compounds permits a major reduction in uranium enrichment, and tests have shown that the silicide fuels perform well under irradiation. Thermal conductivity data are required for analysis of these results and for safety calculations. The data show that silicide-Al dispersion fuels have somewhat better thermal conductivities than U3O-Al dispersions, but their principal advantage is in their increased uranium content. The differences between the thermal conductivities of U3Si and U3Si2 dispersions are small, but the microstructure of the dispersion was found to have a major influence on thermal conductivity. This seems to be associated with the formation of planar porosity defects during the roll bonding process, and differences as large as a factor of four (59 vs. 14 W/m . K) were noted for the samples having equal U3Si2 contents (46 v/o).
Book Synopsis Thermal conductivities of u3si and u3si2-al dispersion fuels by : R. K. Williams
Download or read book Thermal conductivities of u3si and u3si2-al dispersion fuels written by R. K. Williams and published by . This book was released on 1985 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Differential Thermal Analysis Study of U3Si-Al and U3Si2-Al Reactions by :
Download or read book Differential Thermal Analysis Study of U3Si-Al and U3Si2-Al Reactions written by and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: As part of the Reduced Enrichment Research and Test Reactor (RERTR) program, high density uranium compounds are being evaluated as possible replacements for the fuels currently in use. U3Si and U3Si2 powders dispersed in an Al matrix and roll bonded within 6061 Al alloy clad have performed well under irradiation in the ORR. A consideration of the heats of reaction between the silicides and the Al components of a reactor fuel plate has now been addressed. By following standard quantitative differential thermal analysis (DTA) procedures, it has been demonstrated that neither silicide shows any measurable heat of reaction until the solidus temperature of 6061 (582°C) is exceeded. On heating, the exothermic reaction is quenched by the endothermic change of state as the Al species melt. All detectable events take place in the temperature regime from approx. 580 to approx. 660°C. The heats of reaction per gram of fuel ranged from 304 +- 18 J for samples with 32 vol. % U3Si2 in the fuel zone to 486 +- 54 J for samples containing 45 vol. % U3Si in the fuel zone. 6 references, 11 figures, 7 tables.
Book Synopsis Some Recent Observations on the Radiation Behavior of Uranium Silicide Dispersion Fuel by :
Download or read book Some Recent Observations on the Radiation Behavior of Uranium Silicide Dispersion Fuel written by and published by . This book was released on 1988 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt: Addition of B4C burnable poison results in higher plate swelling in both U3Si2 and U3Si-Al dispersion fuel plates and also decreases the blister threshold temperature of these plates. Prolonged annealing of U3Si2-Al fuel plates produced no blister after 696 hours at 400°C. Blister formation started between 257 hours and 327 hours at 425°C and between 115 hours and 210 hours at 450°C. Operation with breached cladding resulted in pillowing of an U3Si-Al fuel plate due to reaction of the fuel core with coolant water. 4 refs., 10 figs., 2 tabs.
Book Synopsis Tem Characterization of Irradiated U3SI2/AL Dispersion Fuel by :
Download or read book Tem Characterization of Irradiated U3SI2/AL Dispersion Fuel written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The silicide dispersion fuel of U3Si2/Al has been recognized as a reasonably good performance fuel for nuclear research and test reactors except that it requires the use of high enrichment uranium. An irradiated U3Si2/Al dispersion fuel (~75% enrichment) from the high flux side of a RERTR-8 (U0R040) plate was characterized using transmission electron microscopy (TEM). The fuel plate was irradiated in the advanced test reactor (ATR) for 105 days. The average irradiation temperature and fission density of the fuel particles for the TEM sample are estimated to be approximately ~110 degrees C and 5.4 x 10-21 f/cm3. The characterization was performed using a 200KV TEM with a LaB6 filament. Detailed microstructural information along with composition analysis is obtained. The results and their implication on the performance of this silicide fuel are discussed.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1995 with total page 782 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis DART Model for Thermal Conductivity of U3Si2 Aluminum Dispersion Fuel by :
Download or read book DART Model for Thermal Conductivity of U3Si2 Aluminum Dispersion Fuel written by and published by . This book was released on with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper describes the primary physical models that form the basis of the DART model for calculating irradiation-induced changes in the thermal conductivity of aluminium dispersion fuel. DART calculations of fuel swelling, pore closure, and thermal conductivity are compared with measured values.
Book Synopsis Performance of Low-enriched U3Si2-aluminum Dispersion Fuel Elements in the Oak Ridge Research Reactor by :
Download or read book Performance of Low-enriched U3Si2-aluminum Dispersion Fuel Elements in the Oak Ridge Research Reactor written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Six high-density, low-enriched U3Si2-Al dispersion fuel elements have been tested in the Oak Ridge Research Reactor (ORR). The elements were geometrically identical to standard ORR elements. The uranium density in the fuel meat ranged between 4.6 and 5.2 Mg/m3. The elements were fabricated by B and W, CERCA, and NUKEM using their normal materials and fabrication practices, with minor modifications necessitated by the new fuel. The U3Si2 contained minor amounts of USi, U3Si and/or uranium solid solution. The elements were irradiated to approximately normal ORR burnup, and three elements were irradiated twice as long, to average burnups of approx. 80% of the initially contained 235U, well above the burnups normally achieved in research and test reactors. Peak burnups of 98% were achieved. Following suitable cooling periods, the elements were subjected to a series of nondestructive and destructive examinations. The behavior of the fuel was found to be entirely consistent with the known irradiation behavior of the constituent phases. The extremely stable swelling behavior of the U3Si2 phase dominated in all cases. The plates showed small, uniform thickness changes. Blister threshold temperatures were greater than or equal to550°C. It is concluded that low-enriched U3Si2-Al dispersion fuel elements will perform at least as well in research and test reactors with power densities up to that of the ORR as the highly enriched UAl(subscript x)-Al and U3O-Al dispersion fuels currently being used. There were no indications that use of this fuel under substantially more stringent conditions might be precluded. 10 refs., 87 figs., 9 tabs.
Book Synopsis The Use of U3Si2 Dispersed in Aluminum in Plate-type Fuel Elements for Research and Test Reactors by :
Download or read book The Use of U3Si2 Dispersed in Aluminum in Plate-type Fuel Elements for Research and Test Reactors written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A high-density fuel based on U3Si2 dispersed in aluminum has been developed and tested for use in converting plate-type research and test reactors from the use of highly enriched uranium to the use of low-enriched uranium. Results of preirradiation testing and the irradiation and postirradiation examination of miniature fuel plates and full-sized fuel elements are summarized. Swelling of the U3Si2 fuel particles is a linear function of the fission density in the particle to well beyond the fission density achievable in low-enriched fuels. U3Si2 particle swelling rate is approximately the same as that of the commonly used UAl(subscript x) fuel particle. The presence of minor amounts of U3Si or uranium solid solution in the fuel result in greater, but still acceptable, fuel swelling. Blister threshold temperatures are at least as high as those of currently used fuels. An exothermic reaction occurs near the aluminum melting temperature, but the measured energy releases were low enough not to substantially worsen the consequences of an accident. U3Si2-aluminum dispersion fuel with uranium densities up to at least 4.8 Mg/m3 is a suitable LEU fuel for typical plate-type research and test reactors. 42 refs., 28 figs., 7 tabs.
Download or read book Thermal Conductivity written by and published by . This book was released on 1988 with total page 606 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Comprehensive Nuclear Materials by :
Download or read book Comprehensive Nuclear Materials written by and published by Elsevier. This book was released on 2020-07-22 with total page 4871 pages. Available in PDF, EPUB and Kindle. Book excerpt: Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field
Book Synopsis Irradiation Mixing of Al Into U3Si by :
Download or read book Irradiation Mixing of Al Into U3Si written by and published by . This book was released on 1995 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt: Thermal and irradiation induced intermixing of uranium silicide reactor fuels with the aluminum cladding is an important consideration in understanding their fission gas and fuel swelling behavior. The authors have used Rutherford backscattering to follow the behavior of an Al thin film on U3Si and U3Si2 during 1.5 MeV Kr ion irradiation at temperatures of 30 and 350 C. After an initial dose during which no intermixing occurs, the Al mixes quickly into U3Si. The threshold dose is believed to be associated with an oxide layer between the Al and the uranium silicide. At 300 C and doses greater than threshold, rates of mixing and aluminide phase growth are extracted.
Book Synopsis Predicted Irradiation Behavior of U Sub 3 O Sub 8 -Al Dispersion Fuels for Production Reactor Applications by :
Download or read book Predicted Irradiation Behavior of U Sub 3 O Sub 8 -Al Dispersion Fuels for Production Reactor Applications written by and published by . This book was released on 1990 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt: Candidate fuels for the new heavy-water production reactor include uranium/aluminum alloy and U3O--Al dispersion fuels. The U3O--Al dispersion fuel would make possible higher uranium loadings and would facilitate uranium recycle. Research efforts on U3O8--Al fuel include in-pile irradiation studies and development of analytical tools to characterize the behavior of dispersion fuels at high-burnup. In this paper the irradiation performance of U3O8--Al is assessed using the mechanistic Dispersion Analysis Research Tool (DART) code. Predictions of fuel swelling and alteration of thermal conductivity are presented and compared with experimental data. Calculational results indicate good agreement with available data where the effects of as-fabricated porosity and U3O8--Al oxygen exchange reactions are shown to exert a controlling influence on irradiation behavior. The DART code is judged to be a useful tool for assessing U3O8--Al performance over a wide range of irradiation conditions. 8 refs., 8 figs., 1 tab.
Book Synopsis Introduction to Computational Plasticity by : Fionn Dunne
Download or read book Introduction to Computational Plasticity written by Fionn Dunne and published by Oxford University Press. This book was released on 2005-06-09 with total page 259 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book gives an introduction to computational plasticity and includes the kinematics of large deformations, together with relevant continuum mechanics. Central to the book is its focus on computational plasticity, and we cover an introduction to the finite element method which includes both quasi-static and dynamic problems. We then go on to describe explicit and implicit implementations of plasticity models in to finite element software. Throughout the book, we describe thegeneral, multiaxial form of the theory but uniquely, wherever possible, reduce the equations to their simplest, uniaxial form to develop understanding of the general theory and, we hope, physical insight. We provide several examples of implicit and explicit implementations of von Mises time-independentand visco-plasticity in to the commercial code ABAQUS (including the fortran coding), which should prove invaluable to research students and practising engineers developing ABAQUS 'UMATs'. The book bridges the gap between undergraduate material on plasticity and existing advanced texts on nonlinear computational mechanics, which makes it ideal for students and practising engineers alike. It introduces a range of engineering applications, including superplasticity, porous plasticity, cyclicplasticity and thermo-mechanical fatigue, to emphasize the subject's relevance and importance.
Book Synopsis Detailed Analysis of Uranium Silicide Dispersion Fuel Swelling by :
Download or read book Detailed Analysis of Uranium Silicide Dispersion Fuel Swelling written by and published by . This book was released on 1989 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt: Swelling of U3Si and U3Si2 is analyzed. The growth of fission gas bubbles appears to be affected by fission rate, fuel loading, and microstructural change taking place in the fuel compounds during irradiation. Several mechanisms are explored to explain the observations. The present work is aimed at a better understanding of the basic swelling phenomenon in order to accurately model irradiation behavior of uranium silicide disperson fuel. 5 refs., 10 figs.
Book Synopsis Nuclear Regulatory Commission Issuances by : U.S. Nuclear Regulatory Commission
Download or read book Nuclear Regulatory Commission Issuances written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1979 with total page 950 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Specification for al-u3si2 dispersion fuel containing gd2o3 as a burnable poison by : D. F. Sears
Download or read book Specification for al-u3si2 dispersion fuel containing gd2o3 as a burnable poison written by D. F. Sears and published by . This book was released on 1996 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
