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Waste Treatment Of Acidic Solutions From The Dissolution Of Irradiated Leu Targets For 99 Mo Production
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Book Synopsis Waste Treatment of Acidic Solutions from the Dissolution of Irradiated LEU Targets for 99-Mo Production by :
Download or read book Waste Treatment of Acidic Solutions from the Dissolution of Irradiated LEU Targets for 99-Mo Production written by and published by . This book was released on 2016 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt: One of the missions of the Reduced Enrichment for Research and Test Reactors (RERTR) program (and now the National Nuclear Security Administrations Material Management and Minimization program) is to facilitate the use of low enriched uranium (LEU) targets for 99Mo production. The conversion from highly enriched uranium (HEU) to LEU targets will require five to six times more uranium to produce an equivalent amount of 99Mo. The work discussed here addresses the technical challenges encountered in the treatment of uranyl nitrate hexahydrate (UNH)/nitric acid solutions remaining after the dissolution of LEU targets. Specifically, the focus of this work is the calcination of the uranium waste from 99Mo production using LEU foil targets and the Modified Cintichem Process. Work with our calciner system showed that high furnace temperature, a large vent tube, and a mechanical shield are beneficial for calciner operation. One- and two-step direct calcination processes were evaluated. The high-temperature one-step process led to contamination of the calciner system. The two-step direct calcination process operated stably and resulted in a relatively large amount of material in the calciner cup. Chemically assisted calcination using peroxide was rejected for further work due to the difficulty in handling the products. Chemically assisted calcination using formic acid was rejected due to unstable operation. Chemically assisted calcination using oxalic acid was recommended, although a better understanding of its chemistry is needed. Overall, this work showed that the two-step direct calcination and the in-cup oxalic acid processes are the best approaches for the treatment of the UNH/nitric acid waste solutions remaining from dissolution of LEU targets for 99Mo production.
Book Synopsis Gas Generation During Waste Treatment of Acidic Solutions from the Dissolution of Irradiated LEU Targets for 99Mo Production by :
Download or read book Gas Generation During Waste Treatment of Acidic Solutions from the Dissolution of Irradiated LEU Targets for 99Mo Production written by and published by . This book was released on 2017 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt: The goal of the Reduced Enrichment for Research and Test Reactors Program is to limit the use of high-enriched uranium (HEU) in research and test reactors by substituting low-enriched uranium (LEU) wherever possible. The work reported here documents our work to develop the calcining technologies and processes that will be needed for 99Mo production using LEU foil targets and the Modified Cintichem Process. The primary concern with the conversion to LEU from HEU targets is that it would result in a five- to six-fold increase in the total uranium. This increase results in more liquid waste from the process. We have been working to minimize the increase in liquid waste and to minimize the impact of any change in liquid waste. Direct calcination of uranium-rich nitric acid solutions generates NO2 gas and UO3 solid. We have proposed two processes for treating the liquid waste from a Modified Cintichem Process with a LEU foil. One is an optimized direct calcination process that is similar to the process currently in use. The other is a uranyl oxalate precipitation process. The specific goal of the work reported here was to characterize and compare the chemical reactions that occur during these two processes. In particular, the amounts and compositions of the gaseous and solid products were of interest. A series of experiments was carried out to show the effects of temperature and the redox potential of the reaction atmosphere. The primary products of the direct calcination process were mixtures of U3O8 and UO3 solids and NO2 gas. The primary products of the oxalate precipitation process were mixtures of U3O8 and UO2 solid and CO2 gas. Higher temperature and a reducing atmosphere tended to favor quadrivalent over hexavalent uranium in the solid product. These data will help producers to decide between the two processes. In addition, the data can be used to design appropriate off-gas systems for pilot and production facilities.
Book Synopsis Processing of LEU Targets for 99Mo Production -- Dissolution of Metal Foils by Nitric-acid by :
Download or read book Processing of LEU Targets for 99Mo Production -- Dissolution of Metal Foils by Nitric-acid written by and published by . This book was released on 1995 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: The first step in processing low-enriched uranium (LEU) targets for production of 99Mo is to dissolve the neutron-irradiated uranium foil coming from the reactor. Appropriate conditions for dissolving the foils were determined by measuring the dissolution rates for uranium foil over a wide range of temperatures and acid concentrations. On the basis of these dissolution rates, the process chemistry, and a model that integrates dissolution rates as a function of temperature and composition, a closed stainless-steel dissolver was designed, built, and tested for dissolving up to 18 g of uranium foil. The results were quite successful, with the uranium foil being dissolved within one hour as desired. To do this, the dissolver temperature must be in the range from 97 to 102 C, and the dissolver solution (cocktail) must have a composition of 3M nitric acid and 2M sulfuric acid. The final dissolver solution is subsequently processed to separate 99Mo from uranium, fission products, and other elements.
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 Processing of LEU Targets for 99Mo Production -- Dissolution of Metal Foil Targets by Alkaline Hydrogen Peroxide by :
Download or read book Processing of LEU Targets for 99Mo Production -- Dissolution of Metal Foil Targets by Alkaline Hydrogen Peroxide written by and published by . This book was released on 1995 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: In FY 1995, the authors started studies on a new process for dissolution of low-enriched uranium (LEU) targets for 99Mo production. In this process, an LEU metal foil target is dissolved in a mixture of sodium hydroxide and hydrogen peroxide, then 99Mo is recovered from the dissolved solution. They focused on the dissolution kinetics to develop a mechanistic model for predicting the products and the rate of uranium dissolution under process conditions. They thoroughly studied the effects of hydrogen peroxide concentration, sodium hydroxide concentration, and temperature on the rate of uranium dissolution. It was found that uranium dissolution can be classified into a low-base (0.2M) and a high-base ( 0.2M) process. In the low-base process, both the equilibrium hydrogen peroxide and hydroxide concentrations affect the rate of uranium dissolution; in the high base process, uranium dissolution is a 0.25th order reaction with respect to the equilibrium hydrogen peroxide. The dissolution activation energy was experimentally determined to be 48.8 kJ/mol. Generally, the rate of uranium dissolution increases to a maximum as the hydroxide concentration is increased from 0.01 to about 1.5M, then it decreases as the hydroxide concentration is further increased. The alkalinity of the dissolution solution is an important factor that affects not only the dissolution rate, but also the amount of radioactive waste.
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 Full-Scale Testing of the Ambient Pressure, Acid-Dissolution Front-End Process for the Current 99Mo Recovery Processes by :
Download or read book Full-Scale Testing of the Ambient Pressure, Acid-Dissolution Front-End Process for the Current 99Mo Recovery Processes written by and published by . This book was released on 2013 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Global Threat Reduction Initiative (GTRI) Conversion Program is actively developing technologies for converting civilian facilities that use high enriched uranium (HEU) to low enriched uranium (LEU) fuels and targets. The conversion of conventional HEU targets to LEU for the production of 99Mo production requires approximately five times the uranium in a target to maintain the 99Mo yield on a per-target basis. Under GTRI, Argonne National Laboratory (Argonne) is developing two frontend options for current 99Mo production processes to allow the use of LEU-foil targets. In both processes, the aim is to produce a frontend product that is compatible with current 99Mo purification operations and will provide the same or a higher yield of 99Mo for the same number of irradiated targets. The two frontend processes under development as part of this project are (1) the dissolution of irradiated LEU foil (up to 250 g in a single batch) and nickel fission recoil barrier in nitric acid at ambient pressure; and (2) the electrochemical dissolution of LEU foil in series of steps that produces an alkaline (basic) solution feed for 99Mo purification. This report describes results from performance tests and design optimization of the ambient pressure, nitric-acid-dissolver system. The design, fabrication, and performance test planning for this system are described in more detail in previous reports (Jerden et al. 2011a, b, 2012). Full-scale demonstrations of both of the frontend processes using irradiated uranium foils are planned to be performed at Oak Ridge National Laboratory this fiscal year.
Book Synopsis Processing of LEU Targets For[sup 99]Mo Production--testing and Modification of the Cintichem Process by :
Download or read book Processing of LEU Targets For[sup 99]Mo Production--testing and Modification of the Cintichem Process written by and published by . This book was released on 2001 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Recent experimental results on testing and modification of the Cintichem process to allow substitution of low enriched uranium (LEU) for high enriched uranium (HEU) targets are presented in this report. The main focus is on[sup 99]Mo recovery and purification by its precipitation with[alpha]-benzoin oxime. Parameters that were studied include concentrations of nitric and sulfuric acids, partial neutralization of the acids, molybdenum and uranium concentrations, and the ratio of[alpha]-benzoin oxime to molybdenum. Decontamination factors for uranium, neptunium, and various fission products were measured. Experiments with tracer levels of irradiated LEU were conducted for testing the[sup 99]Mo recovery and purification during each step of the Cintichem process. Improving the process with additional processing steps was also attempted. The results indicate that the conversion of molybdenum chemical processing from HEU to LEU targets is possible.
Book Synopsis Processing of LEU Targets for 99Mo Production--testing and Modification of the Cintichem Process by :
Download or read book Processing of LEU Targets for 99Mo Production--testing and Modification of the Cintichem Process written by and published by . This book was released on 1995 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Recent experimental results on testing and modification of the Cintichem process to allow substitution of low enriched uranium (LEU) for high enriched uranium (HEU) targets are presented in this report. The main focus is on 99Mo recovery and purification by its precipitation with [alpha]-benzoin oxime. Parameters that were studied include concentrations of nitric and sulfuric acids, partial neutralization of the acids, molybdenum and uranium concentrations, and the ratio of [alpha]-benzoin oxime to molybdenum. Decontamination factors for uranium, neptunium, and various fission products were measured. Experiments with tracer levels of irradiated LEU were conducted for testing the 99Mo recovery and purification during each step of the Cintichem process. Improving the process with additional processing steps was also attempted. The results indicate that the conversion of molybdenum chemical processing from HEU to LEU targets is possible.
Book Synopsis Processing of LEU Targets for 99Mo Production-dissolution of U3Si2 Targets by Alkaline Hydrogen Peroxide by : B. A. Buchholz
Download or read book Processing of LEU Targets for 99Mo Production-dissolution of U3Si2 Targets by Alkaline Hydrogen Peroxide written by B. A. Buchholz and published by . This book was released on 1995* with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Dissolution of Low-enriched UO2 by :
Download or read book Dissolution of Low-enriched UO2 written by and published by . This book was released on 1997 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Some conclusions from this report are: (1) A UO2/Al dispersion target can be successfully dissolved in alkaline peroxide solutions; (2) after destruction of the peroxide recovery of the 99Mo would be nearly identical to existing processes using basic dissolution; (3) a low-enriched UO2/Al dispersion targets could potentially be used for the production of 99Mo; and (4) punched cores from a UO2/Al dispersion target will be irradiated to low-level burnup and effects of this LEU target on the recovery of 99Mo will be investigated. A commercial partner will be sought for full scale demonstrations.
Book Synopsis Progress in Chemical Treatment of LEU Targets by the Modified Cintichem Process by :
Download or read book Progress in Chemical Treatment of LEU Targets by the Modified Cintichem Process written by and published by . This book was released on 1996 with total page 29 pages. Available in PDF, EPUB and Kindle. Book excerpt: Presented here are recent experimental results on tests of a modified Cintichem process for producing 99Mo from low enriched uranium (LEU). Studies were focused in three areas: (1) testing the effects on 99Mo recovery and purity of dissolving LEU foil in nitric acid alone, rather than in the sulfuric/nitric acid mixture currently used, (2) measuring decontamination factors for radionuclide impurities in each purification step, and (3) testing the effects on processing of adding barrier materials to the LEU metal-foil target. The experimental results show that switching from dissolving the target in the sulfuric/nitric mixture to using nitric acid alone should cause no significant difference in 99Mo product yield or purity. Further, the results show that overall decontamination factors for gamma emitters in the LEU-target processing are high enough to meet the purity requirements for the 99Mo product. The results also show that the selected barrier materials, Cu, Fe, and Ni, do not interfere with 99Mo recovery and can be removed during chemical processing of the LEU target.
Book Synopsis Advanced Powder Technology VIII by : Lucio Salgado
Download or read book Advanced Powder Technology VIII written by Lucio Salgado and published by Trans Tech Publications Ltd. This book was released on 2012-08-24 with total page 2080 pages. Available in PDF, EPUB and Kindle. Book excerpt: Selected, peer reviewed papers from the Eighth Latin American Conference on Powder Technology, November 6-9, 2011, Florianópolis, Brazil
Book Synopsis Dissolution of Low-enriched UO{sub 2}/Al Dispersion Plates in Alkaline Peroxide Solution by :
Download or read book Dissolution of Low-enriched UO{sub 2}/Al Dispersion Plates in Alkaline Peroxide Solution written by and published by . This book was released on 1997 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Some conclusions from this report are: (1) A UO2/Al dispersion target can be successfully dissolved in alkaline peroxide solutions; (2) after destruction of the peroxide recovery of the 99Mo would be nearly identical to existing processes using basic dissolution; (3) a low-enriched UO2/Al dispersion targets could potentially be used for the production of 99Mo; and (4) punched cores from a UO2/Al dispersion target will be irradiated to low-level burnup and effects of this LEU target on the recovery of 99Mo will be investigated. A commercial partner will be sought for full scale demonstrations.
Download or read book The Supply of Medical Isotopes written by and published by . This book was released on 2019 with total page 122 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report explores the main reasons behind the unreliable supply of Technetium-99m (Tc-99m) in health-care systems and policy options to address the issue. Tc-99m is used in 85% of nuclear medicine diagnostic scans performed worldwide – around 30 million patient examinations every year. These scans allow diagnoses of diseases in many parts of the human body, including the skeleton, heart and circulatory system, and the brain. Medical isotopes are subject to radioactive decay and have to be delivered just-in-time through a complex supply chain. However, ageing production facilities and a lack of investment have made the supply of Tc-99m unreliable. This report analyses the use and substitutability of Tc-99m in health care, health-care provider payment mechanisms for scans, and the structure of the supply chain. It concludes that the main reasons for unreliable supply are that production is not economically viable and that the structure of the supply chain prevents producers from charging prices that reflect the full costs of production and supply.
Book Synopsis Actinide Separations by : James D. Navratil
Download or read book Actinide Separations written by James D. Navratil and published by . This book was released on 1980 with total page 632 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Processing of LEU Targets For[sup 99]Mo Production -- Demonstration of a Modified Cintichem Process by :
Download or read book Processing of LEU Targets For[sup 99]Mo Production -- Demonstration of a Modified Cintichem Process written by and published by . This book was released on 2001 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Two demonstrations of the use of the Cintichem process on simulated low enriched uranium (LEU,
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