The Thermal Stability of Al-USiAl Dispersion Fuels and Al-U Alloys

Feraday,; Davidson, R. D.; Foo, M.T.; Winegar, J.E.

doi:10.13182/nt82-a32934

Cited by 8 publications

(4 citation statements)

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“…Fuel cores for nuclear research and test reactors are aluminum matrix composites constituted of uranium alloys such as UAl x (mainly UAl 3 ) or U 3 Si 2 dispersed in aluminum powder [1][2][3]. Therefore, reactions between U and Al or between U and Al with another element are of great technical interest.…”

Section: Introductionmentioning

confidence: 99%

Stoichiometry of UAl4

Tougait

Noël

2004

Intermetallics

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Section: Introductionmentioning

confidence: 99%

Stoichiometry of UAl4

Tougait

Noël

2004

Intermetallics

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“…These investigations focus not only on the U-containing compounds used in the fuels, but also on the alloys of U with common elements of structural materials and fission products [1][2][3][4]. (U + Bi) and (U + Sn) molten alloys used as mixed fuel have been investigated by many researchers because of their notable advantages such as high specific power, low costs, better neutron economy, etc.…”

Section: Introductionmentioning

confidence: 99%

Critical evaluation and thermodynamic optimization of the (U + Bi), (U + Si) and (U + Sn) binary systems

Wang

et al. 2016

The Journal of Chemical Thermodynamics

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“…Special design of a tubular aluminium-clad U -AI fuel element[119]. Special design of a tubular aluminium-clad U -AI fuel element[119].…”

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confidence: 99%

U Uranium

Borgstedt¹,

Wedemeyer²

1989

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This work is subject to copyright. ALL rights are reserved, whether the whoLe or part of the materiaL is concerned, specifically those of translation, reprinting, reuse of illustrations, broadcasting, reproduction by photocopying machine or similar means, and storage in data banks. Under §54 of the German Copyright Law where copies are made for other than private use, a fee is payabLe to "VerwertungsgeseLLschafl Wort", Munich. © by Springer-VerLag Berlin HeideLberg 1989 Originally published by Springer-Verlag Berlin Heidelberg New York in 1989. Softcover reprint ofthe hardcover 8th edition 1989The use of registered names, trademarks, etc., in this publication does not impLy, even in the absence of a specific statement, that such names are exempt from the reLevant protective laws and regulations and therefore free for general use. PrefaceThe present voLume describes the alloys and the intermetaLLic compounds of uranium with the main group metaLs -those systems with semimetaLs such as boron and germanium are to be found in corresponding voLumes in uranium C series. In this voLume, main emphasis is given to the binary systems. Ternary systems are onLy deaLt with if there is formation of specific compounds or if there are other important characteristics or reactions. In generaL, the influence of small quantities of a third metaL on a system U-M, e.g., for mechanicaL properties or corrosion effects wiLL not be discussed in order not to extend this voLume excessiveLy.The ternary alloys are described immediateLy after the reLated binary systems. E. g., U-Ga-Ni is found after U-Ga, unLess a pLace after U-Ni couLd be imaginabLe from more systematic reasons (system of the Last position). The preferred order is aLso indicated in the sequence of eLement symboLs within the formuLas of compounds and systems: The compounds/systems reLated to U -AL are written as U -AL -M, etc.The behavior of uranium metaL towards the main group metaLs can be divided into two groups:Practically no soLubility in each other and no compound formation. This is the case for the aLkali and aLkaLine earth systems (except beryllium).OccasionaL formation of severaL compounds with Limited or extensive solid soLubility. This is observed for beryllium and the metaLs of third and fourth main group.The most frequently investigated systems are uranium -beryllium and uranium -aLuminium because of their speciaL scientific (U-Be) and technoLogicaL (U-AL) importance. UBe13, the onLy compound in the binary U -Be system, is one of the very few heavy-fermion compounds. Therefore, its physicaL properties especially were extensiveLy and thoroughLy studied in recent years. This GmeLin voLume gives a compLete and very detailed description of this compound, and at the time of publication, the most updated one.On the other hand, cermets and alloys in the U-AL system are very important as fueL, especially for the high-neutron-fLux nucLear research reactors. This fueL is mainLy based on 235U-enriched uranium on the aLuminium-rich side of the U -AL system, e. g., as UAL 4 ...

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The Thermal Stability of Al-USiAl Dispersion Fuels and Al-U Alloys

Cited by 8 publications

References 1 publication

Stoichiometry of UAl4

Stoichiometry of UAl4

Critical evaluation and thermodynamic optimization of the (U + Bi), (U + Si) and (U + Sn) binary systems

U Uranium

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