Thermal Compatibility Studies of Unirradiated Uranium Silicide Dispersed in Aluminum. [Reduced Enrichment for Research and Test Reactor]. PDF Download
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Languages : en
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Powder metallurgy dispersions of uranium silicides in an aluminum matrix have been developed by the international Reduced Enrichment for Research and Test Reactors program as a new generation of proliferation-resistant fuels. A major issue of concern is the compatibility of the fuel with the matrix material and the dimensional stability of this fuel type. A total of 45 miniplate-type fuel plates were annealed at 400°C for up to 1981 hours. A data base for the thermal compatibility of unirradiated uranium silicide dispersed in aluminum was established. No modification tested of a standard fuel plate showed any significant reduction of the plate swelling. The cause of the thermal growth of silicide fuel plates was determined to be a two-step process: (1) the reaction of the uranium silicide with aluminum to form U(AlSi)3 and (2) the release of hydrogen and subsequent creep and pillowing of the fuel plate. 9 references, 4 figures, 6 tables.
![Thermal Compatibility Studies of Unirradiated Uranium Silicide Dispersed in Aluminum. [Reduced Enrichment for Research and Test Reactor]. PDF](https://books.google.com/books/content/images/frontcover/sztPAQAACAAJ?fife=w80-h100)
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Languages : en
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Book Description
Powder metallurgy dispersions of uranium silicides in an aluminum matrix have been developed by the international Reduced Enrichment for Research and Test Reactors program as a new generation of proliferation-resistant fuels. A major issue of concern is the compatibility of the fuel with the matrix material and the dimensional stability of this fuel type. A total of 45 miniplate-type fuel plates were annealed at 400°C for up to 1981 hours. A data base for the thermal compatibility of unirradiated uranium silicide dispersed in aluminum was established. No modification tested of a standard fuel plate showed any significant reduction of the plate swelling. The cause of the thermal growth of silicide fuel plates was determined to be a two-step process: (1) the reaction of the uranium silicide with aluminum to form U(AlSi)3 and (2) the release of hydrogen and subsequent creep and pillowing of the fuel plate. 9 references, 4 figures, 6 tables.
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Category : Power resources
Languages : en
Pages : 1344
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Category : Power resources
Languages : en
Pages : 676
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Author: Markus H.A. Piro
Publisher: Woodhead Publishing
ISBN: 008102651X
Category : Business & Economics
Languages : en
Pages : 672
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Advances in Nuclear Fuel Chemistry presents a high-level description of nuclear fuel chemistry based on the most recent research and advances. Dr. Markus H.A. Piro and his team of global, expert contributors cover all aspects of both the conventional uranium-based nuclear fuel cycle and non-conventional fuel cycles, including mining, refining, fabrication, and long-term storage, as well as emerging nuclear technologies, such as accident tolerant fuels and molten salt materials. Aimed at graduate students, researchers, academics and practicing engineers and regulators, this book will provide the reader with a single reference from which to learn the fundamentals of classical thermodynamics and radiochemistry. Consolidates the latest research on nuclear fuel chemistry into one comprehensive reference, covering all aspects of traditional and non-traditional nuclear fuel cycles Includes contributions from world-renowned experts from many countries representing government, industry and academia Covers a variety of fuel designs, including conventional uranium dioxide, mixed oxides, research reactor fuels, and molten salt fuels Written by experts with hands-on experience in the development of such designs
Author: Argonne National Laboratory. Materials and Components Technology Division
Publisher:
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Category : Materials
Languages : en
Pages : 184
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Category : Nuclear energy
Languages : en
Pages : 962
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Category : Metallurgy
Languages : en
Pages : 1264
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ISBN:
Category : Science
Languages : en
Pages : 1054
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Author: American Nuclear Society
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Category : Nuclear engineering
Languages : en
Pages : 880
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Author: U.S. Nuclear Regulatory Commission
Publisher:
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Category : Nuclear energy
Languages : en
Pages : 950
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