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Development of Very High-density Low-enriched Uranium Fuels

Development of Very High-density Low-enriched Uranium Fuels PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5

Book Description
The RERTR program has recently begun an aggressive effort to develop dispersion fuels for research and test reactors with uranium densities of 8 to 9 g U/cm3, based on the use of [gamma]-stabilized uranium alloys. Fabrication development teams and facilities are being put into place and preparations for the first irradiation test are in progress. The first screening irradiations are expected to begin in late April 1997 and first results should be available by end of 1997. Discussions with potential international partners in fabrication development and irradiation testing have begun.

Development of Very High-density Low-enriched Uranium Fuels

Development of Very High-density Low-enriched Uranium Fuels PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 5

Book Description
The RERTR program has recently begun an aggressive effort to develop dispersion fuels for research and test reactors with uranium densities of 8 to 9 g U/cm3, based on the use of [gamma]-stabilized uranium alloys. Fabrication development teams and facilities are being put into place and preparations for the first irradiation test are in progress. The first screening irradiations are expected to begin in late April 1997 and first results should be available by end of 1997. Discussions with potential international partners in fabrication development and irradiation testing have begun.

Progress in Developing Very-high-density Low-enriched-uranium Fuels

Progress in Developing Very-high-density Low-enriched-uranium Fuels PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 9

Book Description
Preliminary results from the postirradiation examinations of microplates irradiated in the RERTR-1 and -2 experiments in the ATR have shown several binary and ternary U-MO alloys to be promising candidates for use in aluminum-based dispersion fuels with uranium densities up to 8 to 9 g/cm3. Ternary alloys of uranium, niobium, and zirconium performed poorly, however, both in terms of fuel/matrix reaction and fission-gas-bubble behavior, and have been dropped from further study. Since irradiation temperatures achieved in the present experiments (approximately 70 C) are considerably lower than might be experienced in a high-performance reactor, a new experiment is being planned with beginning-of-cycle temperatures greater than 200 C in 8-g U/cm3 fuel.

Reducing the Use of Highly Enriched Uranium in Civilian Research Reactors

Reducing the Use of Highly Enriched Uranium in Civilian Research Reactors PDF Author: National Academies of Sciences, Engineering, and Medicine
Publisher: National Academies Press
ISBN: 0309379210
Category : Science
Languages : en
Pages : 205

Book Description
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.

Medical Isotope Production Without Highly Enriched Uranium

Medical Isotope Production Without Highly Enriched Uranium PDF Author: National Research Council
Publisher: National Academies Press
ISBN: 0309130395
Category : Medical
Languages : en
Pages : 220

Book Description
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.

Good Practices for Qualification of High Density Low Enriched Uranium Research Reactor Fuels

Good Practices for Qualification of High Density Low Enriched Uranium Research Reactor Fuels PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201043092
Category : History
Languages : en
Pages : 73

Book Description
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.

Impact of Fuel Density on Performance and Economy of Research Reactors

Impact of Fuel Density on Performance and Economy of Research Reactors PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201203205
Category : Technology & Engineering
Languages : en
Pages : 84

Book Description
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.

Uranium Enrichment and Nuclear Weapon Proliferation

Uranium Enrichment and Nuclear Weapon Proliferation PDF Author: Allan S. Krass
Publisher: Routledge
ISBN: 100020054X
Category : Political Science
Languages : en
Pages : 325

Book Description
Originally published in 1983, this book presents both the technical and political information necessary to evaluate the emerging threat to world security posed by recent advances in uranium enrichment technology. Uranium enrichment has played a relatively quiet but important role in the history of efforts by a number of nations to acquire nuclear weapons and by a number of others to prevent the proliferation of nuclear weapons. For many years the uranium enrichment industry was dominated by a single method, gaseous diffusion, which was technically complex, extremely capital-intensive, and highly inefficient in its use of energy. As long as this remained true, only the richest and most technically advanced nations could afford to pursue the enrichment route to weapon acquisition. But during the 1970s this situation changed dramatically. Several new and far more accessible enrichment techniques were developed, stimulated largely by the anticipation of a rapidly growing demand for enrichment services by the world-wide nuclear power industry. This proliferation of new techniques, coupled with the subsequent contraction of the commercial market for enriched uranium, has created a situation in which uranium enrichment technology might well become the most important contributor to further nuclear weapon proliferation. Some of the issues addressed in this book are: A technical analysis of the most important enrichment techniques in a form that is relevant to analysis of proliferation risks; A detailed projection of the world demand for uranium enrichment services; A summary and critique of present institutional non-proliferation arrangements in the world enrichment industry, and An identification of the states most likely to pursue the enrichment route to acquisition of nuclear weapons.

Opportunities and Approaches for Supplying Molybdenum-99 and Associated Medical Isotopes to Global Markets

Opportunities and Approaches for Supplying Molybdenum-99 and Associated Medical Isotopes to Global Markets PDF Author: National Academies of Sciences, Engineering, and Medicine
Publisher: National Academies Press
ISBN: 030946627X
Category : Medical
Languages : en
Pages : 87

Book Description
Participants of the July 17-18, 2017, symposium titled Opportunities and Approaches for Supplying Molybdenum-99 and Associated Medical Isotopes to Global Markets examined current trends in molybdenum-99 production, prospects for new global supplies, and technical, economic, regulatory, and other considerations for supplying molybdenum-99 to global markets. This publication summarizes the presentations and discussions from the symposium.

Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel Production: Fact Sheet

Quadrilateral Cooperation on High-density Low-enriched Uranium Fuel Production: Fact Sheet PDF Author: United States. National Nuclear Security Administration
Publisher:
ISBN:
Category : Nuclear facilities
Languages : en
Pages :

Book Description


High Uranium Density Dispersion Fuel for the Reduced Enrichment of Research and Test Reactors Program

High Uranium Density Dispersion Fuel for the Reduced Enrichment of Research and Test Reactors Program PDF Author: Adam B. Robinson
Publisher:
ISBN:
Category : Uranium alloys
Languages : en
Pages : 118

Book Description
This work describes the fabrication of a high uranium density fuel for the Reduced Enrichment of Research and Test Reactors Program. In an effort to decrease the use of high enriched uranium in research and test reactors around the world, new fuels with high uranium densities must be developed such that low enrichment fuel may be used in its place. Preliminary studies on uranium molybdenum alloys have shown promising results. A uranium molybdenum fuel phase dispersed in a zirconium matrix is proposed and examined in this thesis. Work described herein includes the successful fabrication of materials, preparation of samples, diffusion testing, fuel fabrication, and analysis of the resulting product. The fabrication results appear to be very good and all data collected indicates that this fuel type is fabricable and justifies irradiation testing.