Download or read book EK 10 Dispersion Fuel Elements for Experimental and University Reactors written by Władysław Rutkowski and published by . This book was released on 1965 with total page 26 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Fuel Elements written by Brian R. T. Frost and published by Elsevier. This book was released on 2013-10-22 with total page 284 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear Fuel Elements: Design, Fabrication and Performance is concerned with the design, fabrication, and performance of nuclear fuel elements, with emphasis on fast reactor fuel elements. Topics range from fuel types and the irradiation behavior of fuels to cladding and duct materials, fuel element design and modeling, fuel element performance testing and qualification, and the performance of water reactor fuels. Fast reactor fuel elements, research and test reactor fuel elements, and unconventional fuel elements are also covered. This volume consists of 12 chapters and begins with an overview of nuclear reactors and fuel elements, as well as fuel element design and development based on the reactor operator's approach, materials scientist's approach, and interdisciplinary approach. The reader is then introduced to different types of nuclear fuels and their irradiation behavior, considerations for using cladding and duct materials in fuel element design and development, and fuel element design and modeling. The chapters that follow focus on the testing of fuel element performance, experimental techniques and equipment for testing fuel element designs, and the performance of fuels for water reactors. Fuel elements for gas-cooled reactors, fast reactors, and research and test reactors are also described. The book concludes with an assessment of unconventional fuel elements. This book will be useful to fuel element technologists as well as materials scientists and engineers.

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1970 with total page 1202 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Dispersion Type Fuel Elements for Nuclear Reactors written by Andreĭ Grigorʹevich Samoĭlov and published by . This book was released on 1970 with total page 147 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Dispersion Fuel Elements written by Abe Noel Holden and published by . This book was released on 1967 with total page 276 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1965 with total page 1128 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Report written by Instytut Badań Jądrowych (Poland) and published by . This book was released on 1964 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Dispersion fuel Nuclear Reactor Elements written by A. G. Samoilov and published by . This book was released on 1968 with total page 223 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Report written by Instytut Badań Jądrowych (Poland) and published by . This book was released on 1966 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book A Study of Fast Reactor Fuel Transmutation in a Candidate Dispersion Fuel Design written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Dispersion fuels represent a significant departure from typical ceramic fuels to address swelling and radiation damage in high burnup fuel. Such fuels use a manufacturing process in which fuel particles are encapsulated within a non-fuel matrix. Dispersion fuels have been studied since 1997 as part of an international effort to develop and test very high density fuel types for the Reduced Enrichment for Research and Test Reactors (RERTR) program.[1] The Idaho National Laboratory is performing research in the development of an innovative dispersion fuel concept that will meet the challenges of transuranic (TRU) transmutation by providing an integral fission gas plenum within the fuel itself, to eliminate the swelling that accompanies the irradiation of TRU. In this process, a metal TRU vector produced in a separations process is atomized into solid microspheres. The dispersion fuel process overcoats the microspheres with a mixture of resin and hollow carbon microspheres to create a TRUC. The foam may then be heated and mixed with a metal power (e.g., Zr, Ti, or Si) and resin to form a matrix metal carbide, that may be compacted and extruded into fuel elements. In this paper, we perform reactor physics calculations for a core loaded with the conceptual fuel design. We will assume a "typical" TRU vector and a reference matrix density. We will employ a fuel and core design based on the Advanced Burner Test Reactor (ABTR) design.[2] Using the CSAS6 and TRITON modules of the SCALE system [3] for preliminary scoping studies, we will demonstrate the feasibility of reactor operations. This paper will describe the results of these analyses.

Download or read book Performance of Low enriched U3Si2 aluminum Dispersion Fuel Elements in the Oak Ridge Research Reactor written by G. L. Copeland and published by . This book was released on 1987 with total page 130 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book List of References on Nuclear Energy written by International Atomic Energy Agency and published by . This book was released on 1965-07 with total page 856 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fundamental aspects of nuclear reactor fuel elements written by Donald R. Olander and published by . This book was released on 1976 with total page 551 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Science Abstracts of Poland written by and published by . This book was released on 1965 with total page 326 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Polish Review written by and published by . This book was released on 1966 with total page 546 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Decommissioning Techniques for Research Reactors written by International Atomic Energy Agency and published by . This book was released on 1994 with total page 124 pages. Available in PDF, EPUB and Kindle. Book excerpt: This is the first report published by the IAEA which provides guidance on the preparation and implementation of the decommissioning of different types of research reactor. Different construction and operational features of research reactors have a major impact on the decommissioning techniques required. This report offers information on the conclusions drawn from a number of completed projects and identifies their similarities and differences. It is complemented by a computerized research reactor databank. Staff requirements, decommissioning costs waste activity are presented graphically according to reactor thermal power and integrated energy.

Download or read book Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor written by Willem Frederik Geert van Rooijen and published by IOS Press. This book was released on 2006 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Generation IV Forum is an international nuclear energy research initiative aimed at developing the fourth generation of nuclear reactors, envisaged to enter service halfway the 21st century. One of the Generation IV reactor systems is the Gas Cooled Fast Reactor (GCFR), the subject of study in this thesis. The Generation IV reactor concepts should improve all aspects of nuclear power generation. Within Generation IV, the GCFR concept specifically targets sustainability of nuclear power generation. The Gas Cooled Fast Reactor core power density is high in comparison to other gas cooled reactor concepts. Like all nuclear reactors, the GCFR produces decay heat after shut down, which has to be transported out of the reactor under all circumstances. The layout of the primary system therefore focuses on using natural convection Decay Heat Removal (DHR) where possible, with a large coolant fraction in the core to reduce friction losses.