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High Density Fuel Development For Research Reactors
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Book Synopsis High Density Fuel Development for Research Reactors by :
Download or read book High Density Fuel Development for Research Reactors written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: An international effort to develop, qualify, and license high and very high density fuels has been underway for several years within the framework of multi-national RERTR programs. The current development status is the result of significant contributions from many laboratories, specifically CNEA in Argentina, AECL in Canada, CEA in France, TUM in Germany, KAERI in Korea, VNIIM, RDIPE, IPPE, NCCP and RIARR in Russia, INL, ANL and Y-12 in USA. These programs are mainly engaged with UMo dispersion fuels with densities from 6 to 8 gU/cm3 (high density fuel) and UMo monolithic fuel with density as high as 16 gU/cm3 (very high density fuel). This paper, mainly focused on the French & US programs, gives the status of high density UMo fuel development and perspectives on their qualification.
Book Synopsis Impact of Fuel Density on Performance and Economy of Research Reactors by : IAEA
Download or read book Impact of Fuel Density on Performance and Economy of Research Reactors written by IAEA and published by International Atomic Energy Agency. This book was released on 2021-04-22 with total page 118 pages. Available in PDF, EPUB and Kindle. Book excerpt: Research reactor fuel technology continues to evolve, driven in part by international efforts to develop high density fuels to enable the conversion of more reactors from highly enriched uranium (HEU) to low enriched uranium (LEU) fuels. These high density fuels may offer economic benefits for research reactors, despite being more expensive initially, because they offer the prospect of higher per-assembly burnup, thus reducing the number of assemblies that must be procured, and more flexibility in terms of spent fuel management compared to the currently qualified and commercially available LEU silicide fuels. Additionally, these new fuels may offer better performance characteristics. This publication provides a preliminary evaluation of the impacts on research reactor performance and fuel costs from using high density fuel. Several case studies are presented and compared to illustrate these impacts.
Book Synopsis Impact of Fuel Density on Performance and Economy of Research Reactors by : International Atomic Energy Agency
Download or read book Impact of Fuel Density on Performance and Economy of Research Reactors written by International Atomic Energy Agency and published by . This book was released on 2021 with total page 84 pages. Available in PDF, EPUB and Kindle. Book excerpt: Research reactor fuel technology continues to evolve, driven in part by international efforts to develop high density fuels to enable the conversion of more reactors from highly enriched uranium (HEU) to low enriched uranium (LEU) fuels. These high density fuels may offer economic benefits for research reactors, despite being more expensive initially, because they offer the prospect of higher per-assembly burnup, thus reducing the number of assemblies that must be procured, and more flexibility in terms of spent fuel management compared to the currently qualified and commercially available LEU silicide fuels. Additionally, these new fuels may offer better performance characteristics. This publication provides a preliminary evaluation of the impacts on research reactor performance and fuel costs from using high density fuel. Several case studies are presented and compared to illustrate these impacts.
Author :National Academies of Sciences, Engineering, and Medicine Publisher :National Academies Press ISBN 13 :0309379210 Total Pages :205 pages Book Rating :4.3/5 (93 download)
Book Synopsis Reducing the Use of Highly Enriched Uranium in Civilian Research Reactors by : National Academies of Sciences, Engineering, and Medicine
Download or read book Reducing the Use of Highly Enriched Uranium in Civilian Research Reactors written by National Academies of Sciences, Engineering, and Medicine and published by National Academies Press. This book was released on 2016-02-12 with total page 205 pages. Available in PDF, EPUB and Kindle. Book excerpt: The continued presence of highly enriched uranium (HEU) in civilian installations such as research reactors poses a threat to national and international security. Minimization, and ultimately elimination, of HEU in civilian research reactors worldwide has been a goal of U.S. policy and programs since 1978. Today, 74 civilian research reactors around the world, including 8 in the United States, use or are planning to use HEU fuel. Since the last National Academies of Sciences, Engineering, and Medicine report on this topic in 2009, 28 reactors have been either shut down or converted from HEU to low enriched uranium fuel. Despite this progress, the large number of remaining HEU-fueled reactors demonstrates that an HEU minimization program continues to be needed on a worldwide scale. Reducing the Use of Highly Enriched Uranium in Civilian Research Reactors assesses the status of and progress toward eliminating the worldwide use of HEU fuel in civilian research and test reactors.
Book Synopsis Good Practices for Qualification of High Density Low Enriched Uranium Research Reactor Fuels by : International Atomic Energy Agency
Download or read book Good Practices for Qualification of High Density Low Enriched Uranium Research Reactor Fuels written by International Atomic Energy Agency and published by . This book was released on 2009 with total page 73 pages. Available in PDF, EPUB and Kindle. Book excerpt: The conversion of research and test reactors from the use of fuel containing highly enriched uranium (HEU) to fuel that employs low-enriched uranium (LEU) has become an important issue in many Member States. The IAEA has supported several projects and activities assisting in the reduction of the use of HEU. However, no comprehensive publication addressing the rationale of qualification of these fuels had yet been available. Developed in order to meet this need, the present publication provides good practices and points of reference for the type, quality and completeness of the information to be generated in order to ensure acceptable performance of high density LEU fuels to be used in research reactors. Furthermore, it elaborates on the development and qualification of high density fuels of the type used in most research and test reactors and assesses the different approaches to the qualification process.
Book Synopsis Medical Isotope Production Without Highly Enriched Uranium by : National Research Council
Download or read book Medical Isotope Production Without Highly Enriched Uranium written by National Research Council and published by National Academies Press. This book was released on 2009-06-27 with total page 220 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book is the product of a congressionally mandated study to examine the feasibility of eliminating the use of highly enriched uranium (HEU2) in reactor fuel, reactor targets, and medical isotope production facilities. The book focuses primarily on the use of HEU for the production of the medical isotope molybdenum-99 (Mo-99), whose decay product, technetium-99m3 (Tc-99m), is used in the majority of medical diagnostic imaging procedures in the United States, and secondarily on the use of HEU for research and test reactor fuel. The supply of Mo-99 in the U.S. is likely to be unreliable until newer production sources come online. The reliability of the current supply system is an important medical isotope concern; this book concludes that achieving a cost difference of less than 10 percent in facilities that will need to convert from HEU- to LEU-based Mo-99 production is much less important than is reliability of supply.
Book Synopsis Development of Advanced High Uranium Density Fuels for Light Water Reactors by :
Download or read book Development of Advanced High Uranium Density Fuels for Light Water Reactors written by and published by . This book was released on 2016 with total page 58 pages. Available in PDF, EPUB and Kindle. Book excerpt: This work conducts basic materials research (fabrication, radiation resistance, thermal conductivity, and corrosion response) on U3Si2 and UN, two high uranium density fuel forms that have a high potential for success as advanced light water reactor (LWR) fuels. The outcome of this proposed work will serve as the basis for the development of advance LWR fuels, and utilization of such fuel forms can lead to the optimization of the fuel performance related plant operating limits such as power density, power ramp rate and cycle length.
Author :International Atomic Energy Agency Publisher :International Atomic Energy Agency ISBN 13 :9789201450104 Total Pages :108 pages Book Rating :4.4/5 (51 download)
Book Synopsis Applications of Research Reactors by : International Atomic Energy Agency
Download or read book Applications of Research Reactors written by International Atomic Energy Agency and published by International Atomic Energy Agency. This book was released on 2014 with total page 108 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication is a comprehensive study that reviews the current situation in a great number of applications of research reactors. It revises the contents of IAEA TECDOC-1234, The Applications of Research Reactors, giving detailed updates on each field of research reactor uses worldwide. Reactors of all sizes and capabilities can benefit from the sharing of current practices and research enabled via this updated version, which describes the requirements for practicing methods as diverse as neutron activation analysis, education and training, neutron scattering and neutron imaging, silicon doping and radioisotope production, material/fuel irradiation and testing, and some others. Many underutilised research reactors can learn how to diversify their technical capabilities, staff and potential commercial partners and users seeking research reactor services and products. The content of the publication has also been strengthened in terms of current issues facing the vast majority of research reactors by including sections describing user and customer relations as well as strategic planning considerations.
Book Synopsis Update on US High Density Fuel Fabrication Development by :
Download or read book Update on US High Density Fuel Fabrication Development written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Second generation uranium molybdenum fuel has shown excellent in-reactor irradiation performance. This metallic fuel type is capable of being fabricated at much higher loadings than any presently used research reactor fuel. Due to the broad range of fuel types this alloy system encompasses--fuel powder to monolithic foil and binary fuel systems to multiple element additions--significant amounts of research and development have been conducted on the fabrication of these fuels. This paper presents an update of the US RERTR effort to develop fabrication techniques and the fabrication methods used for the RERTR-9A miniplate test.
Book Synopsis Nuclear Fuel Elements by : Brian R. T. Frost
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.
Book Synopsis Neutronic Performance of High-density LEU Fuels in Water-moderated and Water-reflected Research Reactors by :
Download or read book Neutronic Performance of High-density LEU Fuels in Water-moderated and Water-reflected Research Reactors written by and published by . This book was released on 1996 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt: At the Reduced Enrichment for Research and Test Reactors (RERTR) meeting in September 1994, Durand reported that the maximum uranium loading attainable with U3Si2 fuel is about 6.0 g U/cm3. The French Commissariat a l'Energie Atomique (CEA) plan to perform irradiation tests with 5 plates at this loading. Compagnie pour L'Etude et La Realisation de Combustibles Atomiques (CERCA) has also fabricated a few uranium nitride (UN) plates with a uranium density in the fuel meat of 7.0 g/cm3 and found that UN is compatible with the aluminum matrix at temperatures below 500 C. High density dispersion fuels proposed for development include U-Zr(4 wt%)-Nb(2 wt%), U-Mo(5 wt%), and U-Mo(9 wt%). The purpose of this note is to examine the relative neutronic behavior of these high density fuels in a typical light water-reflected and water-moderated MTR-type research reactor. The results show that a dispersion of the U-Zr-Nb alloy has the most favorable neutronic properties and offers the potential for uranium densities greater than 8.0 g/cm3. On the other hand, UN is the least reactive fuel because of the relatively large 14N(n, p) cross section. For a fixed value of k{sub eff}, the required 235U loading per fuel element is least for the U-Zr-Nb fuel and steadily increases for the U-Mo(5%), U-Mo(9%), and UN fuels. Because of volume fraction limitations, the UO2 dispersions are only useful for uranium densities below 5.0 g/cm3. In this density range, however, UO2 is more reactive than U3Si2.
Book Synopsis Relative Neutronic Performance of Proposed High-density Dispersion Fuels in Water-moderated and D2O-reflected Research Reactors by :
Download or read book Relative Neutronic Performance of Proposed High-density Dispersion Fuels in Water-moderated and D2O-reflected Research Reactors written by and published by . This book was released on 1996 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper provides an overview of the neutronic performance of an idealized research reactor using several high density LEU fuels that are being developed by the RERTR program. High-density LEU dispersion fuels are needed for new and existing high-performance research reactors and to extend the lifetime of fuel elements in other research reactors. This paper discusses the anticipated neutronic behavior of proposed advanced fuels containing dispersions of U3Si2, UN, U2Mo and several uranium alloys with Mo, or Zr and Nb. These advanced fuels are ranked based on the results of equilibrium depletion calculations for a simplified reactor model having a small H2O-cooled core and a D2O reflector. Plans have been developed to fabricate and irradiate several uranium alloy dispersion fuels in order to test their stability and compatibility with the matrix material and to establish practical loading limits.
Book Synopsis Summaries of Fuels and Materials Development Program by : William L. R. Rice
Download or read book Summaries of Fuels and Materials Development Program written by William L. R. Rice and published by . This book was released on 1963 with total page 286 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :United States. Energy Research and Development Administration. Division of Waste Management, Production, and Reprocessing Publisher : ISBN 13 : Total Pages :50 pages Book Rating :4.:/5 (31 download)
Book Synopsis The Management and Storage of Commercial Power Reactor Wastes by : United States. Energy Research and Development Administration. Division of Waste Management, Production, and Reprocessing
Download or read book The Management and Storage of Commercial Power Reactor Wastes written by United States. Energy Research and Development Administration. Division of Waste Management, Production, and Reprocessing and published by . This book was released on 1976 with total page 50 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Research Reactors for the Development of Materials and Fuels for Innovative Nuclear Energy Systems by : International Atomic Energy Agency
Download or read book Research Reactors for the Development of Materials and Fuels for Innovative Nuclear Energy Systems written by International Atomic Energy Agency and published by . This book was released on 2017-11-28 with total page 27 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication presents an overview of research reactor capabilities and capacities in the development of fuels and materials for innovative nuclear reactors, such as GenIV reactors. The compendium provides comprehensive information on the potential for materials and fuel testing research of 30 research reactors, both operational and in development. This information includes their power levels, mode of operation, current status, availability and historical overview of their utilization. A summary of these capabilities and capacities is presented in the overview tables of section 6. Papers providing a technical description of the research reactors, including their specific features for utilization are collected as profiles on a CD-ROM and represent an integral part of this publication. The publication is intended to foster wider access to information on existing research reactors with capacity for advanced material testing research and thus ensure their increased utilization in this particular domain. It is expected that it can also serve as a supporting tool for the establishment of regional and international networking through research reactor coalitions and IAEA designated international centres based on research reactors.
Book Synopsis US Progress on Property Characterization to Support LEU U-10 Mo Monolithic Fuel Development by :
Download or read book US Progress on Property Characterization to Support LEU U-10 Mo Monolithic Fuel Development written by and published by . This book was released on 2016 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The US High Performance Research Reactor program is pursuing development and qualification of a new high density monolithic LEU fuel to facilitate conversion of five higher power research reactors located in the US (ATR, HFIR, NBSR, MIT and MURR). In order to support fabrication development and fuel performance evaluations, new testing capabilities are being developed to evaluate the properties of fuel specimens. Residual stress and fuel-cladding bond strength are two characteristics related to fuel performance that are being investigated. In this overview, new measurement capabilities being developed to assess these characteristics in both fresh and irradiated fuel are described. Progress on fresh fuel testing is summarized and on-going hot-cell implementation efforts to support future PIE campaigns are detailed. It is anticipated that benchmarking of as-fabricated fuel characteristics will be critical to establishing technical bases for specifications that optimize fuel fabrication and ensure acceptable in-reactor fuel performance.
Book Synopsis Development of a Monolithic Research Reactor Fuel Type at Argonne National Laboratory by : C. R. Clark
Download or read book Development of a Monolithic Research Reactor Fuel Type at Argonne National Laboratory written by C. R. Clark and published by . This book was released on 2004 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Reduced Enrichment for Research and Test Reactors (RERTR) program has been tasked with the conversion of research reactors from highly enriched to low-enriched uranium (LEU). To convert several high power reactors, monolithic fuel, a new fuel type, is being developed. This fuel type replaces the standard fuel dispersion with a fuel alloy foil, which allows for fuel densities far in excess of that found in dispersion fuel. The single-piece fuel foil also contains a significantly lower interface area between the fuel and the aluminum in the plate than the standard fuel type, limiting the amount of detrimental fuel-aluminum interaction that can occur. Implementation of monolithic fuel is dependant on the development of a suitable fabrication method as traditional roll-bonding techniques are inadequate.
