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

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.

This report presents state-of-the art information on the effects of nuclear radiation on ceramic reactor fuel materials that are being used or being considered for use in various types of reactors. The materials discussed include uranium oxides, uranium carbides, uranium mononitride, uranium silicides, plutonium oxide, and plutonium carbide. The report presents data in the form of tables and curves for physical damage incurred by the fuel materials as a result of their exposure to nuclear radiation.

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