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ISBN 13 :
Total Pages : 15 pages
Book Rating : 4.:/5 (929 download)
Download or read book A General Evaluation of the Irradiation Behavior of Dispersion Fuels written by and published by . This book was released on 1991 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
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ISBN 13 :
Total Pages : 15 pages
Book Rating : 4.:/5 (727 download)
Download or read book A General Evaluation of the Irradiation Behavior of Dispersion Fuels written by and published by . This book was released on 1991 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: This document discusses the irradiation behavior of aluminum-based dispersion fuels and evaluates metallurgical processes that control the dispersion behavior. Phase transformations and microstructural changes resulting from fuel-matrix interactions and the effect of fissioning in fuel are discussed.
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ISBN 13 :
Total Pages : 7 pages
Book Rating : 4.:/5 (727 download)
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.
Author : D. W. White (Jr.)
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ISBN 13 :
Total Pages : 62 pages
Book Rating : 4.3/5 (91 download)
Download or read book Irradiation Behavior of Dispersion Fuels written by D. W. White (Jr.) and published by . This book was released on 1957 with total page 62 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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ISBN 13 :
Total Pages : 17 pages
Book Rating : 4.:/5 (684 download)
Download or read book Initial Assessment of Radiation Behavior of Very-high-density Low-enriched-uranium Fuels written by and published by . This book was released on 1999 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: Results from the postirradiation examinations of microplates irradiated in the RERTR-1 and -2 experiments in the ATR have shown several binary and ternary U-Mo alloys to be promising candidates for use in aluminum-based dispersion fuels with uranium densities up to 8 to 9 g/cm3. Ternary alloys of uranium, niobium, and zirconium performed poorly, however, both in terms of fuel/matrix reaction and fission-gas-bubble behavior, and have been dropped from further study. Since irradiation temperatures achieved in the present experiments (approximately 70 C)are considerably lower than might be experienced in a high-performance reactor, a new experiment is being planned with beginning-of-cycle temperatures greater than 200 C in 8-g U/cm3 fuel.
Download or read book Correlation Between Annealing and Irradiation Behavior of Dispersion Fuels written by and published by . This book was released on 1987 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Studying the effects of annealing of scaled-down dispersion fuel plates is an important part of the data base for fuel performance. One of the most critical aspects of fuel performance is the stability of a fuel/matrix dispersion which is usually measured by volumetric changes of the fuel zone. A correlation has been proposed that fission-induced amorphization is responsible for the instability of the fuel and that such transformations can be predicted by the thermodynamic properties of the fuel. It is proposed that annealing studies may be used as a screening test for new fuels for which no thermodynamic properties have been measured and/or no irradiation data are available. Estimations of irradiation performance could be obtained faster and without the expense of irradiating the fuels under investigation. Miniature fuel plates were fabricated by standard procedures and annealed at 400°C for up to 1981 hrs in a resistance wound furnace. At periodic intervals the plates were removed and the fuel zone volumes were calculated based on immersion density measurement data. 7 refs., 1 tab.
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ISBN 13 :
Total Pages : 544 pages
Book Rating : 4.0/5 ( download)
Download or read book Energy Research Abstracts written by and published by . This book was released on 1994-06 with total page 544 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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ISBN 13 :
Total Pages : 21 pages
Book Rating : 4.:/5 (727 download)
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.
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ISBN 13 :
Total Pages : 12 pages
Book Rating : 4.:/5 (685 download)
Download or read book Comparison of Irradiation Behavior of Different Uranium Silicide Dispersion Fuel Element Designs written by and published by . This book was released on 1995 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Calculations of fuel swelling of U3SiAl-Al and U3Si2 were performed for various dispersion fuel element designs. Breakaway swelling criteria in the form of critical fuel volume fractions were derived with data obtained from U3SiAl-Al plate irradiations. The results of the analysis show that rod-type elements remain well below the pillowing threshold. However, tubular fuel elements, which behave essentially like plates, will likely develop pillows or blisters at around 90% 235U burnup. The U3Si2-Al compounds demonstrate stable swelling behavior throughout the entire burnup range for all fuel element designs.
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ISBN 13 :
Total Pages : 5 pages
Book Rating : 4.:/5 (684 download)
Download or read book Irradiation Behavior of Uranium-molybdenum Dispersion Fuel written by and published by . This book was released on 2001 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Irradiation Behavior of Aluminum-base Fuel Dispersions written by and published by . This book was released on 1973 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
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ISBN 13 :
Total Pages : 29 pages
Book Rating : 4.:/5 (684 download)
Download or read book Irradiation Behavior of Uranium Oxide-aluminum Dispersion Fuel written by and published by . This book was released on 1996 with total page 29 pages. Available in PDF, EPUB and Kindle. Book excerpt: An oxide version of the DART code has been generated in order to assess the irradiation behavior of UO2-Al dispersion fuel. The aluminum-fuel interaction models were developed based on U3O-Al irradiation data. Deformation of the fuel element occurs due to fuel particle swelling driven by both solid and gaseous fission products, as well as a consequence of the interaction between the fuel particles and the aluminum matrix. The calculations show, that with the assumption that the correlations derived from U3O are valid for UO2, the LEU UO2-Al with a 42% fuel volume loading (4 gm/cc) irradiated at fuel temperatures greater than 413 K should undergo breakaway swelling at core burnups greater than about 1.12 x 1027 fissions m−3 ((approximately) 63% 235U burnup).
Author : United States. Arms Control and Disarmament Agency
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ISBN 13 :
Total Pages : 332 pages
Book Rating : 4.:/5 (327 download)
Download or read book U.S. Arms Control and Disarmament Agency 1990 and 1991 Annual Reports written by United States. Arms Control and Disarmament Agency and published by . This book was released on 1993 with total page 332 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : United States. Arms Control and Disarmament Agency
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ISBN 13 :
Total Pages : 336 pages
Book Rating : 4.3/5 (121 download)
Download or read book U.S. Arms Control and Disarmament Agency ... Annual Report written by United States. Arms Control and Disarmament Agency and published by . This book was released on 1992 with total page 336 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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ISBN 13 :
Total Pages : 81 pages
Book Rating : 4.:/5 (251 download)
Download or read book Materialy Postojannoj stratigrafičeskoj Komissi po karbonu SSSR. written by and published by . This book was released on 1971 with total page 81 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : U.S. Nuclear Regulatory Commission
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ISBN 13 :
Total Pages : 950 pages
Book Rating : 4.3/5 (129 download)
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:
Download or read book Irradiation Behavior of Miniature Experimental Uranium Silicide Fuel Plates written by and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Uranium silicides, because of their relatively high uranium density, were selected as candidate dispersion fuels for the higher fuel densities required in the Reduced Enrichment Research and Test Reactor (RERTR) Program. Irradiation experience with this type of fuel, however, was limited to relatively modest fission densities in the bulk from, on the order of 7 x 102° cm−3, far short of the approximately 20 x 102° cm−3 goal established for the RERTR program. The purpose of the irradiation experiments on silicide fuels on the ORR, therefore, was to investigate the intrinsic irradiation behavior of uranium silicide as a dispersion fuel. Of particular interest was the interaction between the silicide particles and the aluminum matrix, the swelling behavior of the silicide particles, and the maximum volume fraction of silicide particles that could be contained in the aluminum matrix.
