Alloys of Uranium with Alkali Metals, Alkaline Earths, and Elements of Main Groups III and IV. The description of uranium and its compounds, for which the Gmelin Institute has started a series of volumes supplementing the main volume of 1936, follows in its arrangement closely the order chosen for the transuranium volumes. Part A treats "The Element", Part B "The Metal and its Alloys", Part C "The Compounds", Part D "The Chemistry in Solution", and finally Part E "The Coordination Compounds". Part E, "The Coordination Compounds" comprises two volumes which already have been finished and are available - completely written in English. Series A comprises 7 volumes which are all available. Series C will comprise 14 volumes of which only volume 6 is missing. Series D consists of 4 volumes dealing with the chemistry in solution, which already have been finished and are available. The present volume describes the alloys and the intermetallic compounds with the metals of main groups I to IV - those systems with semimetals such as boron and germanium are to be found in corresponding volumes in Uranium C series. In the volume B 2 main emphasis is given to the binary systems. The most frequently investigated systems are uranium-beryllium and uranium-aluminium because of their special scientific (U-Be) and technological (U-Al) importance.

The present volume Uranium C12 covers the binary and polynary carbides of uranium, including ternary carbides with nonmetals like the carbide oxides and carbide nitrides U(C,O) and U(C,N). The binary carbide UC and especially the mixed carbide (UO.80PUO.20)C are of special importance due to their potential as the fuel for advanced .. Fast Breeder Reactors" because of properties such as the short doubling time, the high fissionable material density, and the good thermal conductivity. On the other hand, the dicarbide UC is of interest for .. High 2 Temperature Reactors", especially in the form of the mixed carbide (U . Th . )C . For O80 o20 2 the first time, India used mixed uranium-plutonium carbide (U . PU .)C as the fuel for its O3 O7 own newly developed 15 MW Fast Breeder Reactor at Kalpakkam, south of Madras. el Because of the technological importance of the uranium carbides a lot of data were published only in reports. In most cases, it was the aim of these less-scientifically based studies to promote the carbide fuel development on an economical basis. The lack of analyti cal data on the purity of the samples, missing characterization of the present phases, etc., hQINever, does not allow the discussion of the results of such references in this handbook. Therefore, only reliable publications were cited. For the technical fabrication of uranium carbides and their irradiation behavior, see Volumes A3 and A4 of this Handbook.

The present volume A4 of the "Uranium" series of the Gmelin Handbook deals with two very important technological aspects of the nuclear fuel cycle: - the behavior of fuel elements during burnup in a nuclear reactor, and - the reprocessing of spent fuel to recover the non-fissioned uranium and newly created materials. The usefullifetime of a fuel element in a nuclear reactor depends strongly on the change of its chemical and physical properties during irradiation. Properties like thermal conductivity, swelling, creep, and oxygen-to-metal ratio are strongly affected by the intense neutron field and the energetic fission products. Furthermore, the high temperature gradient in a fuel element also produces alterations of the initial fuel. such as densification or U: Pu segregation. All of these effects are thoroughly discussed for the different kinds of fuels to be used in modern nuclear reactors today or in the future. The vast amount of very often Contradietory results in sometimes difficultly obtainable Iiterature has been summarized to create a compendium in this field with the two sections, on oxide and on carbide and nitride fuels, respectively. The chapters on reprocessing of spent fuels deal only with fuel elements of the uranium 235 thorium fuel cycle and with those containing fuel highly enriched in U. The treatment of U0 2 and (U,Pu)0 has already been given in the transuranic element series.

This edited volume Uranium: Safety, Resources, Separation, and Thermodynamic Calculation is a collection of reviewed and relevant research chapters, offering a comprehensive overview of recent developments in the study of uranium. This publication aims at providing a thorough overview of the latest research efforts by international authors on uranium studies and opens new possible research paths for further novel developments.

An important prerequisite to the long-term use of nuclear energy is information on uranium ore deposits from which uranium can be economically exploited. Hence the basic purpose of this book is to present an overview of uranium geology, data characteristic for uranium deposits, and a synthesis of these data in the form of a typological classification of uranium deposits supported by more detailed descriptions of selected uranium districts and deposits. An additional goal is to provide access for the interested reader to the voluminous literature on uranium geology. Therefore a register of bibliography as global as possible, extending beyond the immediate need for this book, is provided. The volume presented here was not originally designed as a product for its own sake. It evolved as a by-product during decades of active uranium exploration and was compiled thanks to a request by the Springer Publishing Company. Routine research work on identifying characteristic features and recognition criteria of uranium deposits, combined with associated modeling of types of deposits for reapplication in exploration, provided the data bank. The publisher originally asked for a book on uranium deposits structured as a combined text- and reference book. The efforts to condense all the text into a single publication were soon doomed. The material grew out of all feasible proportions for a book of acceptable size and price, a wealth of data on uranium geology and related geosciences having become available during the past decade, too vast for one volume.

This volume gathers and presents a massive collection of data on the location, quality and accessibility of uranium resources in nearly every region of the globe. This exhaustive, up-to-date reference is designed for practical use and arranged by four geographic regions: Asia, USA and Latin America, Europe, and Australia-Oceania and Africa.

This sudy is the second major contribution by UNEP to the scientific debate on the environmental risks and behaviour of DU associated with the use of depleted uranium wepons in a real combat situation.