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Author : A. H. Chura
Publisher :
ISBN 13 :
Total Pages : 199 pages
Book Rating : 4.:/5 (81 download)
Download or read book Safety Analysis of Enriched Uranium Processing written by A. H. Chura and published by . This book was released on 19?? with total page 199 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : H. T. Williams
Publisher :
ISBN 13 :
Total Pages : 204 pages
Book Rating : 4.3/5 (91 download)
Download or read book Safety Analysis of Enriched Uranium Processing written by H. T. Williams and published by . This book was released on 1960 with total page 204 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 40 pages
Book Rating : 4.3/5 (121 download)
Download or read book Status of Highly Enriched Uranium Processing Capability at Building 9212 Oak Ridge Y-12 Plant written by and published by . This book was released on 1996 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Finis S. Patton
Publisher :
ISBN 13 :
Total Pages : 300 pages
Book Rating : 4.E/5 ( download)
Download or read book Enriched uranium processing written by Finis S. Patton and published by . This book was released on 1963 with total page 300 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 19 pages
Book Rating : 4.:/5 (929 download)
Download or read book Criticality Safety Analysis of Highly Enriched Uranium Storage in Steel Tubes Separated by Concrete (U) written by and published by . This book was released on 1992 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Allan S. Krass
Publisher : Routledge
ISBN 13 : 100020054X
Total Pages : 325 pages
Book Rating : 4.0/5 (2 download)
Download or read book Uranium Enrichment and Nuclear Weapon Proliferation written by Allan S. Krass and published by Routledge. This book was released on 2020-11-20 with total page 325 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Author : Benjamin Rickman
Publisher :
ISBN 13 :
Total Pages : 40 pages
Book Rating : 4.:/5 (981 download)
Download or read book Fuel Handling Accident Analysis for the University of Missouri Research Reactors High Enriched Uranium to Low Enriched Uranium Fuel Conversion Initiative written by Benjamin Rickman and published by . This book was released on 2015 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt: In accordance with the 1986 amendment concerning licenses for research and test reactors, the MU Research Reactor (MURR) is planning to convert from using High-Enriched Uranium (HEU) fuel to the use of Low-Enriched Uranium (LEU) fuel. Since the approval of a new LEU fuel that could meet the MURR's per- formance demands, the next phase of action for the fuel conversion process is to create a new Safety Analysis Report (SAR) with respect to the LEU fuel. A component of the SAR includes the Maximum Hypothetical Accident (MHA) and accidents that qualify under the class of Fuel Handling Accidents (FHA). In this work, the dose to occupational staat the MURR is calculated for the FHAs. The radionuclide inventory for the proposed LEU fuel was calculated using the ORIGEN2 point-depletion code linked to the MURR neutron spectrum. The MURR spectrum was generated from a Monte Carlo Neutron transPort (MCNP) simulation. The coupling of these codes create MONTEBURNS, a time-dependent burnup code. The release fraction from each FHA within this analysis was estab- lished by the methodology of the 2006 HEU SAR, which was accepted by the NRC. The actual dose methodology was not recorded in the HEU SAR, so a conservative path was chosen. In compliance to NUREG 1537, when new methodology is used in a HEU to LEU analysis, it is necessary to re-evaluate the HEU accident. The Total Eective Dose Equivalent (TEDE) values were calculated in addi- tion to the whole body dose and thyroid dose to operation personnel. The LEU FHA occupational TEDE dose was 349 mrem which is under the NRC regula- tory occupational dose limit of 5 rem TEDE, and under the LEU MHA limit of 403 mrem. The re-evaluated HEU FHA occupational TEDE dose was 235 mrem,which is above the HEU MHA TEDE dose of 132 mrem. Since the new method- ology produces a dose that is larger than the HEU MHA, we can safely assume that it is more conservative than the previous, unspecied dose.
Author : J. D. McLendon
Publisher :
ISBN 13 :
Total Pages : 13 pages
Book Rating : 4.:/5 (828 download)
Download or read book Nuclear Safety in the Unirradiated Processing Phases of Enriched Uranium Fuel Cycles written by J. D. McLendon and published by . This book was released on 1958 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : IAEA (Corporate Author)
Publisher :
ISBN 13 :
Total Pages : 100 pages
Book Rating : 4.:/5 (12 download)
Download or read book Safety of Conversion Facilities and Uranium Enrichment Facilities Specific Safety Guide written by IAEA (Corporate Author) and published by . This book was released on 2010 with total page 100 pages. Available in PDF, EPUB and Kindle. Book excerpt: This Safety Guide supplements the Safety Requirements publication on Safety of Fuel Cycle Facilities and addresses all the stages in the life cycle of conversion facilities (CFs) and enrichment facilities (EFs), with emphasis placed on design and operation. It describes the actions, conditions and procedures for meeting safety requirements and deals specifically with the handling, processing and storage of depleted, natural and low enriched uranium. The publication is intended to be of use to designers, operating organizations and regulators for ensuring the safety of conversion and enrichment.
Author :
Publisher :
ISBN 13 :
Total Pages : 675 pages
Book Rating : 4.:/5 (965 download)
Download or read book Low-enriched Uranium High-density Target Project. Compendium Report written by and published by . This book was released on 2016 with total page 675 pages. Available in PDF, EPUB and Kindle. Book excerpt: At present, most 99Mo is produced in research, test, or isotope production reactors by irradiation of highly enriched uranium targets. To achieve the denser form of uranium needed for switching from high to low enriched uranium (LEU), targets in the form of a metal foil (~125-150 μm thick) are being developed. The LEU High Density Target Project successfully demonstrated several iterations of an LEU-fission-based Mo-99 technology that has the potential to provide the world's supply of Mo-99, should major producers choose to utilize the technology. Over 50 annular high density targets have been successfully tested, and the assembly and disassembly of targets have been improved and optimized. Two target front-end processes (acidic and electrochemical) have been scaled up and demonstrated to allow for the high-density target technology to mate up to the existing producer technology for target processing. In the event that a new target processing line is started, the chemical processing of the targets is greatly simplified. Extensive modeling and safety analysis has been conducted, and the target has been qualified to be inserted into the High Flux Isotope Reactor, which is considered above and beyond the requirements for the typical use of this target due to high fluence and irradiation duration.
Author :
Publisher :
ISBN 13 :
Total Pages : 16 pages
Book Rating : 4.:/5 (684 download)
Download or read book Low Enriched Uranium Fuel Conversion and Fuel Shipping Guide written by and published by . This book was released on 1997 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: The analysis of reactor core physics and thermal hydraulics was completed in 1993. A supplement to the Final Safety Analysis Report describing the results of these analyses was submitted to the Nuclear Regulatory Commission along with proposed Technical Specifications in May, 1993. Discussions with the NRC staff led to a submittal of revised proposed Technical Specifications in February, 1994. The analytical work is complete. A second portion of the grant was to develop a fuel shipping guide for university research reactors. Such a guide was developed and is available for use by the research reactor community.
Author :
Publisher :
ISBN 13 :
Total Pages : 14 pages
Book Rating : 4.:/5 (685 download)
Download or read book Unreviewed Safety Question Determination for TOPAZ II Uranium Fuel Pellet Production at the Plutonium Handling Facility (PF-4), Technical Area 55, Los Alamos National Laboratory written by and published by . This book was released on 1993 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: Enriched uranium oxide, nitride, and carbide fuel pellets have been produced at PF-4 since the facility became operational in the late 1970s. The TOPAZ II reactors require fuel enriched to 97% uranium-235. Approximately 75 kilograms (kgs) of uranium will be processed per year in support of this program. The amount of fuel processed per year at PF-4 will not be increased for these programs, but the batch size will be increased to approximately 3 kgs of uranium. The current DOE-approved Final Safety Analysis Report (FSAR) calls for batches containing 45 grams (gms) of plutonium-239 and 172 gms of uranium-235. The impact of increasing the uranium batch size on the facility authorization basis is analyzed in the attached Safety Evaluation Worksheet. In addition, the structural modification for the transformer and vacuum pump installation, required to support the operation, is evaluated. Based on the attached Safety Evaluation, it has been determined that the change in uranium batch size does not constitute an Unreviewed Safety Question (USQ), the increase in uranium batch size does not increase the probability or consequences of any accidents previously analyzed and does not create the possibility for a new type of accident or reduce the margin of safety in the Operational Safety Requirements (OSRs). Similarly, the structural modifications required for the transformer and vacuum pump installation do not increase the probability or consequence of any accident previously analyzed and do not create the possibility for a new type of accident or reduce any margin of safety in the OSRS.
Author :
Publisher :
ISBN 13 :
Total Pages : 173 pages
Book Rating : 4.:/5 (967 download)
Download or read book Conversion Preliminary Safety Analysis Report for the NIST Research Reactor written by and published by . This book was released on 2015 with total page 173 pages. Available in PDF, EPUB and Kindle. Book excerpt: The NIST Center for Neutron Research (NCNR) is a reactor-laboratory complex providing the National Institute of Standards and Technology (NIST) and the nation with a world-class facility for the performance of neutron-based research. The heart of this facility is the NIST research reactor (aka NBSR); a heavy water moderated and cooled reactor operating at 20 MW. It is fueled with high-enriched uranium (HEU) fuel elements. A Global Threat Reduction Initiative (GTRI) program is underway to convert the reactor to low-enriched uranium (LEU) fuel. This program includes the qualification of the proposed fuel, uranium and molybdenum alloy foil clad in an aluminum alloy, and the development of the fabrication techniques. This report is a preliminary version of the Safety Analysis Report (SAR) that would be submitted to the U.S. Nuclear Regulatory Commission (NRC) for approval prior to conversion. The report follows the recommended format and content from the NRC codified in NUREG-1537, "Guidelines for Preparing and Reviewing Applications for the Licensing of Non-power Reactors," Chapter 18, "Highly Enriched to Low-Enriched Uranium Conversions." The emphasis in any conversion SAR is to explain the differences between the LEU and HEU cores and to show the acceptability of the new design; there is no need to repeat information regarding the current reactor that will not change upon conversion. Hence, as seen in the report, the bulk of the SAR is devoted to Chapter 4, Reactor Description, and Chapter 13, Safety Analysis.
Author :
Publisher :
ISBN 13 :
Total Pages : 119 pages
Book Rating : 4.:/5 (958 download)
Download or read book Criticality Safety Evaluation for the Advanced Test Reactor Enhanced Low Enriched Uranium Fuel Elements written by and published by . This book was released on 2016 with total page 119 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Global Threat Reduction Initiative (GTRI) convert program is developing a high uranium density fuel based on a low enriched uranium (LEU) uranium-molybdenum alloy. Testing of prototypic GTRI fuel elements is necessary to demonstrate integrated fuel performance behavior and scale-up of fabrication techniques. GTRI Enhanced LEU Fuel (ELF) elements based on the ATR-Standard Size elements (all plates fueled) are to be fabricated for testing in the Advanced Test Reactor (ATR). While a specific ELF element design will eventually be provided for detailed analyses and in-core testing, this criticality safety evaluation (CSE) is intended to evaluate a hypothetical ELF element design for criticality safety purposes. Existing criticality analyses have analyzed Standard (HEU) ATR elements from which controls have been derived. This CSE documents analysis that determines the reactivity of the hypothetical ELF fuel elements relative to HEU ATR elements and whether the existing HEU ATR element controls bound the ELF element. The initial calculations presented in this CSE analyzed the original ELF design, now referred to as Mod 0.1. In addition as part of a fuel meat thickness optimization effort for reactor performance other designs have been evaluated. As of early 2014 the most current conceptual designs are Mk1A and Mk1B that were previously referred to as conceptual designs Mod 0.10 and Mod 0.11, respectively. Revision 1 evaluates the reactivity of the ATR HEU Mark IV elements for a comparison with the Mark VII elements.
Author : National Research Council
Publisher : National Academies Press
ISBN 13 : 0309130395
Total Pages : 220 pages
Book Rating : 4.3/5 (91 download)
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.
Author : International Atomic Energy Agency
Publisher :
ISBN 13 : 9781523129980
Total Pages : 0 pages
Book Rating : 4.1/5 (299 download)
Download or read book Safety of Uranium Fuel Fabrication Facilities: Specific Safety Guide written by International Atomic Energy Agency and published by . This book was released on 2010 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: This Safety Guide supplements the Safety Requirements publication Safety of Fuel Cycle Facilities, and addresses all the stages in the life cycle of uranium fuel fabrication facilities (UFFFs), with emphasis being placed on design and operation. It describes the actions, conditions and procedures for meeting safety requirements and deals specifically with the handling, processing and storage of low enriched uranium that has a 235U concentration of no more than 6%, derived from natural, highly enriched or reprocessed uranium. The publication is intended to be of use to designers, operating organizations and regulators to ensure the safety of UFFFs.Contents: 1. Introduction; 2. General safety recommendations; 3. Site evaluation; 4. Design; 5. Construction; 6. Commissioning; 7. Operation; 8. Decommissioning; Annexes.
Author : National Academies of Sciences, Engineering, and Medicine
Publisher : National Academies Press
ISBN 13 : 0309445310
Total Pages : 264 pages
Book Rating : 4.3/5 (94 download)
Download or read book Molybdenum-99 for Medical Imaging written by National Academies of Sciences, Engineering, and Medicine and published by National Academies Press. This book was released on 2016-11-28 with total page 264 pages. Available in PDF, EPUB and Kindle. Book excerpt: The decay product of the medical isotope molybdenum-99 (Mo-99), technetium-99m (Tc-99m), and associated medical isotopes iodine-131 (I-131) and xenon-133 (Xe-133) are used worldwide for medical diagnostic imaging or therapy. The United States consumes about half of the world's supply of Mo-99, but there has been no domestic (i.e., U.S.-based) production of this isotope since the late 1980s. The United States imports Mo-99 for domestic use from Australia, Canada, Europe, and South Africa. Mo-99 and Tc-99m cannot be stockpiled for use because of their short half-lives. Consequently, they must be routinely produced and delivered to medical imaging centers. Almost all Mo-99 for medical use is produced by irradiating highly enriched uranium (HEU) targets in research reactors, several of which are over 50 years old and are approaching the end of their operating lives. Unanticipated and extended shutdowns of some of these old reactors have resulted in severe Mo-99 supply shortages in the United States and other countries. Some of these shortages have disrupted the delivery of medical care. Molybdenum-99 for Medical Imaging examines the production and utilization of Mo-99 and associated medical isotopes, and provides recommendations for medical use.
