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Thermal Hydraulic Optimization For High Production Of Low Enriched Uranium Based Molybdenum 99
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Book Synopsis Thermal-hydraulic Optimization for High Production of Low-enriched Uranium Based Molybdenum-99 by : Jeffrey William Scott
Download or read book Thermal-hydraulic Optimization for High Production of Low-enriched Uranium Based Molybdenum-99 written by Jeffrey William Scott and published by . This book was released on 2009 with total page 136 pages. Available in PDF, EPUB and Kindle. Book excerpt: Globally, more than 20 million samples of technetium-99 are used annually to diagnose many different forms of cancer. Despite this, there are only four main nuclear reactors worldwide that produce molybdenum-99, the parent isotope of technetium-99m. In an attempt to address the growing demand, as well as to motivate the current reactors to stop using high-enriched uranium, the University of Missouri Research Reactor (MURR) has begun to produce molybdenum-99 using low-enriched uranium. The fission of uranium-235, for which one of the products is molybdenum-99, generates approximately 2 kW of heat per 4-gram target. Continually removing this heat from the fission reaction is the limiting factor in the high-volume production process. The objective of this thesis is to find a reactor wedge setup with maximum rate of heat removal, thereby maximizing the amount of molybdenum-99 that can be created in the reactor. To maximize heat transfer, a quasi 1-D analytic model, calibrated numerically, is created to hydraulically and thermally model the coolant flow through the current reactor setup. Using flow network modeling (FNM), this analytic model is expanded to analyze other potential geometries that could maximize heat transfer. The findings show that for a single channel under the existing reactor configuration, a maximum of 19.18 kW can be dispersed. By opening the drain and slightly shrinking the channel diameter, this can be improved to 22.77 kW. When the system is expanded to 10 parallel channels and the drain is fully opened, over 250 kW can theoretically be achieved, though the neutronics of the MURR reactor will likely limit this.
Book Synopsis Thermal-mechanical Analysis of Targets for High Volume Production of Molybdenum-99 Using Low-enriched Uranium by : Kyler K. Turner
Download or read book Thermal-mechanical Analysis of Targets for High Volume Production of Molybdenum-99 Using Low-enriched Uranium written by Kyler K. Turner and published by . This book was released on 2009 with total page 110 pages. Available in PDF, EPUB and Kindle. Book excerpt: Techenetium-99m is diagnostic radioactive medical isotope that is currently used 30,000 times a day in the United States. All supplies of techenetium-99m's parent isotope molybdenum-99 currently originate from nuclear reactor facilities located in foreign countries and use highly enriched uranium (HEU). The University of Missouri Research Reactor (MURR) is exploring the feasibility of high volume molybdenum-99 production at its facility. Current molybdenum-99 production uses HEU in a powder dispersion target. The powder dispersion method, conventionally used for fuel rods and plates, combines fine particles of aluminum and HEU that are bonded into a rigid plate during irradiation. In accordance with the Global Threat Reduction Initiative all uranium used in future molybdenum-99 production will use low enriched uranium (LEU). Unfortunately LEU has a much low fissionable density then HEU which makes the dispersion process economically unviable. A design approach to increase the LEU density is to use a target that is based on LEU foil. The foil design places a LEU foil between either two concentric annular aluminum cylinders or two aluminum plates which are pressed and welded together to produce a structure that allows for easy removal and processing. The drawback of these designs is the thermal contact resistance between the LEU and aluminum cladding during irradiative heating is very sensitive to the target design, manufacture, and irradiation holder. This thesis explores those thermal-mechanical design issues for both the cylindrical target design and the plate target design. Analytical, numerical and experimental studies are used to assess the mechanical deformation for these structures and its effect on the target's thermal contact resistance.
Book Synopsis The Thermal-mechanical Analysis of Targets for the High Volume Production of Molybdenum-99 Using a Low-enriched Uranium Metal Foil by : Kyler K. Turner
Download or read book The Thermal-mechanical Analysis of Targets for the High Volume Production of Molybdenum-99 Using a Low-enriched Uranium Metal Foil written by Kyler K. Turner and published by . This book was released on 2012 with total page 195 pages. Available in PDF, EPUB and Kindle. Book excerpt: Molybdenum-99 diagnostic imaging is the most commonly practiced procedure in nuclear medicine today with the majority molybdenum-99 produced with proliferation sensitive HEU. International and domestic efforts to develop non-HEU production techniques have taking the first steps toward establishing a new non-HEU molybdenum-99 based supply chain. The focus of the research presented in this work is on the analysis of a new high U-235 density LEU based molybdenum-99 production target. Converting directly to LEU using current manufacturing techniques greatly reduces the molybdenum-99 yield per target making high volume production uneconomical. The LEU based foil target analyzed in this research increases the yield per target making economic high volume production with LEU possible. The research analyzed the thermal-mechanical response of an LEU foil target during irradiation. Thermal-mechanical studies focused on deflections and stresses to assess the probability of target failure. Simpler analytical models were used to determine the proper shape of the target and to benchmark the numerical modeling software. Numerical studies using Abaqus focused on analyzing various heating and cooling conditions and assessing the effects of curvature on the target. Finally, experiments were performed to simulate low power heating and further benchmark the models. The results from all of these analyses indicate a LEU foil target could survive irradiation depending on the conditions seen during irradiation.
Book Synopsis Feasibility of Producing Molybdenum-99 on a Small Scale Using Fission of Low Enriched Uranium Or Neutron Activation of Natural Molybdenum by : International Atomic Energy Agency
Download or read book Feasibility of Producing Molybdenum-99 on a Small Scale Using Fission of Low Enriched Uranium Or Neutron Activation of Natural Molybdenum written by International Atomic Energy Agency and published by . This book was released on 2015-02-17 with total page 180 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :International Atomic Energy Agency Publisher :IAEA Nuclear Energy ISBN 13 :9789201377104 Total Pages :60 pages Book Rating :4.3/5 (771 download)
Book Synopsis Non-HEU Production Technologies for Molybdenum-99 and Technetium-99m by : International Atomic Energy Agency
Download or read book Non-HEU Production Technologies for Molybdenum-99 and Technetium-99m written by International Atomic Energy Agency and published by IAEA Nuclear Energy. This book was released on 2013 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt: Technetium-99m (99mTc) is used in approximately 85% of diagnostic imaging procedures in nuclear medicine worldwide. Interruptions in the supply of Molybdenum (99Mo), which is used to produce 99mTc, prompted governments and international agencies to step up efforts to identify both short- and long-term solutions to supply shortages. These calls for actions resulted in economic and technology studies on the 99Mo supply chain. The present publication supports global efforts to eliminate the civilian use of highly enriched uranium in 99Mo/99Tc production and proposes several alternative/supplementary technologies.
Book Synopsis A Nuclear Reactor and Chemical Processing Design for Production of Molybdenum-99 with Crystalline Uranyl Nitrate Hexahydrate Fuel by : Gary Michael Stange
Download or read book A Nuclear Reactor and Chemical Processing Design for Production of Molybdenum-99 with Crystalline Uranyl Nitrate Hexahydrate Fuel written by Gary Michael Stange and published by . This book was released on 2016 with total page 264 pages. Available in PDF, EPUB and Kindle. Book excerpt: Medical radioisotopes are used in tens of millions of procedures every year to detect and image a wide variety of maladies and conditions in the human body. The most widely-used diagnostic radioisotope is technetium-99m, a metastable isomer of technetium-99 that is generated by the radioactive decay of molybdenum-99. For a number of reasons, the supply of molybdenum-99 has become unreliable and the techniques used to produce it have become unattractive. This has spurred the investigation of new technologies that avoid the use of highly enriched uranium to produce molybdenum-99 in the United States, where approximately half of the demand originates. The first goal of this research is to develop a critical nuclear reactor design powered by solid, discrete pins of low enriched uranium. Analyses of single-pin heat transfer and whole-core neutronics are performed to determine the required specifications. Molybdenum-99 is produced directly in the fuel of this reactor and then extracted through a series of chemical processing steps. After this extraction, the fuel is left in an aqueous state. The second goal of this research is to describe a process by which the uranium may be recovered from this spent fuel solution and reconstituted into the original fuel form. Fuel recovery is achieved through a crystallization step that generates solid uranyl nitrate hexahydrate while leaving the majority of fission products and transuranic isotopes in solution. This report provides background information on molybdenum-99 production and crystallization chemistry. The previously unknown thermal conductivity of the fuel material is measured. Following this is a description of the modeling and calculations used to develop a reactor concept. The operational characteristics of the reactor core model are analyzed and reported. Uranyl nitrate crystallization experiments have also been conducted, and the results of this work are presented here. Finally, a process flow scheme for uranium recovery is examined, in part qualitatively and in part quantitatively, based upon the preceding data garnered through literature review, modeling, and experimentation. The sum of this research is meant to allow for a complete understanding of the process flow, from the beginning of one production cycle to the beginning of another.
Book Synopsis Thermal Hydraulics Analysis of the MIT Research Reactor in Support of a Low Enrichment Uranium (LEU) Core Conversion by : Yu-Chih Ko (Ph. D.)
Download or read book Thermal Hydraulics Analysis of the MIT Research Reactor in Support of a Low Enrichment Uranium (LEU) Core Conversion written by Yu-Chih Ko (Ph. D.) and published by . This book was released on 2008 with total page 290 pages. Available in PDF, EPUB and Kindle. Book excerpt: The MIT research reactor (MITR) is converting from the existing high enrichment uranium (HEU) core to a low enrichment uranium (LEU) core using a high-density monolithic UMo fuel. The design of an optimum LEU core for the MIT reactor is evolving. The objectives of this study are to benchmark the in-house computer code for the MITR, and to perform the thermal hydraulic analyses in support of the LEU design studies. The in-house multi-channel thermal-hydraulics code, MULCH-II, was developed specifically for the MITR. This code was validated against PLTEMP for steady-state analysis, and RELAP5 and temperature measurements for the loss of primary flow transient. Various fuel configurations are evaluated as part of the LEU core design optimization study. The criteria adopted for the LEU thermal hydraulics analysis for this study are the limiting safety system settings (LSSS), to prevent onset of nucleate boiling during steady-state operation, and to avoid a clad temperature excursion during the loss of flow transient. The benchmark analysis results showed that the MULCH-II code is in good agreement with other computer codes and experimental data, and hence it is used as the main tool for this study. In ranking the LEU core design options, the primary parameter is a low power peaking factor in order to increase the LSSS power and to decrease the maximum clad temperature during the transient. The LEU fuel designs with 15 to 18 plates per element, fuel thickness of 20 mils, and a hot channel factor less than 1.76 are shown to comply with these thermal-hydraulic criteria. The steady-state power can potentially be higher than 6 MW, as requested in the power upgrade submission to the Nuclear Regulatory Commission.
Book Synopsis Thermal-hydraulic Aspects of the Use of Low Enrichment Uranium Fuel in the MIT Research Reactor by : Joseph B. Gehret
Download or read book Thermal-hydraulic Aspects of the Use of Low Enrichment Uranium Fuel in the MIT Research Reactor written by Joseph B. Gehret and published by . This book was released on 1984 with total page 304 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Production of MO-99 Using Low-enriched Uranium Silicide by :
Download or read book Production of MO-99 Using Low-enriched Uranium Silicide written by and published by . This book was released on 1994 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Technical Basis in Support of the Conversion of the University of Missouri Research Reactor (MURR) Core from Highly-enriched to Low-enriched Uranium-steady-state Thermal-hydraulic Analysis by :
Download or read book Technical Basis in Support of the Conversion of the University of Missouri Research Reactor (MURR) Core from Highly-enriched to Low-enriched Uranium-steady-state Thermal-hydraulic Analysis written by and published by . This book was released on 2013 with total page 97 pages. Available in PDF, EPUB and Kindle. Book excerpt: The thermal performance of the proposed low-enriched uranium (LEU) core for the University of Missouri Research Reactor (MURR) during steady-state operation is predicted.
Download or read book Абхазия written by and published by . This book was released on 2011 with total page 574 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Thermal Hydraulic Limits Analysis for the Massachusetts Institute of Technology Research Reactor Low Enrichment Uranium Core Conversion Using Statistical Propagation of Parametric Uncertainties by : Keng-Yen Chiang
Download or read book Thermal Hydraulic Limits Analysis for the Massachusetts Institute of Technology Research Reactor Low Enrichment Uranium Core Conversion Using Statistical Propagation of Parametric Uncertainties written by Keng-Yen Chiang and published by . This book was released on 2012 with total page 171 pages. Available in PDF, EPUB and Kindle. Book excerpt: The MIT Research Reactor (MITR) is evaluating the conversion from highly enriched uranium (HEU) to low enrichment uranium (LEU) fuel. In addition to the fuel element re-design from 15 to 18 plates per element, a reactor power upgraded from 6 MW to 7 MW is proposed in order to maintain the same reactor performance of the HEU core. Previous approaches in analyzing the impact of engineering uncertainties on thermal hydraulic limits via the use of engineering hot channel factors (EHCFs) were unable to explicitly quantify the uncertainty and confidence level in reactor parameters. The objective of this study is to develop a methodology for MITR thermal hydraulic limits analysis by statistically combining engineering uncertainties in order to eliminate unnecessary conservatism inherent in traditional analyses. This methodology was employed to analyze the Limiting Safety System Settings (LSSS) for the MITR LEU core, based on the criterion of onset of nucleate boiling (ONB). Key parameters, such as coolant channel tolerances and heat transfer coefficients, were considered as normal distributions using Oracle Crystal Ball for the LSSS evaluation. The LSSS power is determined with 99.7% confidence level. The LSSS power calculated using this new methodology is 9.1 MW, based on core outlet coolant temperature of 60 'C, and primary coolant flow rate of 1800 gpm, compared to 8.3 MW obtained from the analytical method using the EHCFs with same operating conditions. The same methodology was also used to calculate the safety limit (SL) to ensure that adequate safety margin exists between LSSS and SL. The criterion used to calculate SL is the onset of flow instability. The calculated SL is 10.6 MW, which is 1.5 MW higher than LSSS, permitting sufficient margin between LSSS and SL.
Book Synopsis Mo-99 Production from a Low Enriched Uranium Sulfate Solution by :
Download or read book Mo-99 Production from a Low Enriched Uranium Sulfate Solution written by and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
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)
Book Synopsis Molybdenum-99 for Medical Imaging by : National Academies of Sciences, Engineering, and Medicine
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.
Book Synopsis Analysis of Molybdenum-99 Production Capability in the Materials Test Station by :
Download or read book Analysis of Molybdenum-99 Production Capability in the Materials Test Station written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The United States of America currently relies on foreign suppliers to meet all of it needs for molybdenum-99 (Mo-99) used in medical diagnostic procedures. The current US demand is at least 5000 six-day curies per week. Neutronics calculations have been performed to assess whether the proposed Materials Test Station (MTS) could potentially generate Mo-99. Two target material options have been explored for Mo-99 production in the MTS: low enriched uranium (LEU) and Tc-99. For LEU, scoping calculations indicate that MTS can supply nearly half of the current US demand with only minor neutronic impact on the MTS primary mission. For the Tc-99 option, the MTS could produce about one-tenth of the US demand.
Book Synopsis Cyclotron Based Production of Technetium-99m by : International Atomic Energy Agency
Download or read book Cyclotron Based Production of Technetium-99m written by International Atomic Energy Agency and published by . This book was released on 2017 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication presents a comprehensive overview of the technologies involved in the production of cyclotron based 99mTc. These would include techniques relevant to preparation of targets, irradiation of targets under high beam currents, target processing, target recovery and quality control of the final product. The publication provides broad information, well supported with references, on improved production routes and improved separation and purification of cyclotron based 99mTc. These approaches achieve high specific activity and chemical purity of 99mTc suitable for labelling molecules of medical interest and also enable spare capacity to be available at medical cyclotron centres. The readership of this publication is scientists interested in translating this technology to practice, technologists already working with cyclotrons wanting to enhance the utility of the existing machines and managers who are in the process of setting up facilities in their countries. Students working towards higher level degrees in related fields may also benefit from this publication.
Book Synopsis Advances in High Temperature Gas Cooled Reactor Fuel Technology by : International Atomic Energy Agency
Download or read book Advances in High Temperature Gas Cooled Reactor Fuel Technology written by International Atomic Energy Agency and published by . This book was released on 2012-06 with total page 639 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.
