Author: W. E. Schortmann
Publisher:
ISBN:
Category : Dissolution (Chemistry)
Languages : en
Pages : 132
Book Description
Kinetics of the Dissolution of Uranium Dioxide in Carbonate-bicarbonate Solutions
Author: W. E. Schortmann
Publisher:
ISBN:
Category : Dissolution (Chemistry)
Languages : en
Pages : 132
Book Description
Publisher:
ISBN:
Category : Dissolution (Chemistry)
Languages : en
Pages : 132
Book Description
The Use of Powdered Specimens for Studying the Kinetics of Dissolution
Author: W. E. Schortmann
Publisher:
ISBN:
Category : Dissolution (Chemistry)
Languages : en
Pages : 74
Book Description
Publisher:
ISBN:
Category : Dissolution (Chemistry)
Languages : en
Pages : 74
Book Description
Dissolution of Uranium Dioxide Microspheres in Carbonate and Hydrogen Peroxide Solutions
Author: Timothy G. Adams
Publisher:
ISBN:
Category : Carbonates
Languages : en
Pages : 77
Book Description
Uranium dioxide has been used in industry both as a fuel for power reactors and as a target for the production of radioisotopes. One of the most important radioisotopes produced using these targets is molybdenum-99 (Mo-99, 65.94hr half-life), which is the parent isotope to technetium-99m (Tc-99m, 6.01hr half-life), a radioisotope used in 70% of diagnostic medical isotope procedures performed in the United States of America. [1] [2] Molybdenum-99, produced by either the thermal neutron fission of uranium-235 in nuclear reactors or by neutron activation of molybdenum-98, is purified, packaged, and shipped to hospitals worldwide. The maximal activity of Tc-99m is reached in 22.9hrs, so it can be milked from the parent Mo-99 repeatedly. Mo-99 is one of many fission products generated during the thermal neutron fission of uranium-235. For production of Mo-99, irradiation targets based on metallic uranium, uranium alloys, or uranium dioxide are produced. After neutron irradiation in a reactor, the uranium target must first be dissolved in a suitable medium. This has traditionally been done using boiling nitric acid solutions. In literature and in industry, the use of alkaline solutions, specifically carbonate salt solutions combined with hydrogen peroxide, are being explored as an alternative to the nitric acid based dissolution process. The carbonate-peroxide dissolution scheme has several advantages over traditional nitric acid dissolutions including less damage to equipment during operation and smaller volumes of waste produced during process. This thesis research work explores the initial dissolution rates of uranium dioxide in carbonate medium containing hydrogen peroxide. Effect of three different counter cations- ammonium, sodium, and potassium - on the dissolution behavior of uranium was investigated. The kinetic factors of dissolution, activation energy, frequency factor, and reaction order with respect to both the carbonate salt and hydrogen peroxide were found for each of these systems. Information in this thesis is organized into six chapters and list of cited literature sources.
Publisher:
ISBN:
Category : Carbonates
Languages : en
Pages : 77
Book Description
Uranium dioxide has been used in industry both as a fuel for power reactors and as a target for the production of radioisotopes. One of the most important radioisotopes produced using these targets is molybdenum-99 (Mo-99, 65.94hr half-life), which is the parent isotope to technetium-99m (Tc-99m, 6.01hr half-life), a radioisotope used in 70% of diagnostic medical isotope procedures performed in the United States of America. [1] [2] Molybdenum-99, produced by either the thermal neutron fission of uranium-235 in nuclear reactors or by neutron activation of molybdenum-98, is purified, packaged, and shipped to hospitals worldwide. The maximal activity of Tc-99m is reached in 22.9hrs, so it can be milked from the parent Mo-99 repeatedly. Mo-99 is one of many fission products generated during the thermal neutron fission of uranium-235. For production of Mo-99, irradiation targets based on metallic uranium, uranium alloys, or uranium dioxide are produced. After neutron irradiation in a reactor, the uranium target must first be dissolved in a suitable medium. This has traditionally been done using boiling nitric acid solutions. In literature and in industry, the use of alkaline solutions, specifically carbonate salt solutions combined with hydrogen peroxide, are being explored as an alternative to the nitric acid based dissolution process. The carbonate-peroxide dissolution scheme has several advantages over traditional nitric acid dissolutions including less damage to equipment during operation and smaller volumes of waste produced during process. This thesis research work explores the initial dissolution rates of uranium dioxide in carbonate medium containing hydrogen peroxide. Effect of three different counter cations- ammonium, sodium, and potassium - on the dissolution behavior of uranium was investigated. The kinetic factors of dissolution, activation energy, frequency factor, and reaction order with respect to both the carbonate salt and hydrogen peroxide were found for each of these systems. Information in this thesis is organized into six chapters and list of cited literature sources.
Uranium Dioxide
Author: J. Belle
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 744
Book Description
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 744
Book Description
A/CONF.15/P
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 20
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 20
Book Description
The Kinetics of the Dissolution of Uraninite in Carbonate Solutions Under Oxidizing Conditions and Its Applications to the Environmental Hazards of Uranium Solution Mining
Author: Alice L. Ronk
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Nuclear Science Abstracts
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 956
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 956
Book Description
A Kinetic Study of the Dissolution of UO2 in Carbonate Solutions
Author: Ray L. Pearson
Publisher:
ISBN:
Category : Leaching
Languages : en
Pages : 88
Book Description
Publisher:
ISBN:
Category : Leaching
Languages : en
Pages : 88
Book Description
Advances in Nuclear Fuel Chemistry
Author: Markus H.A. Piro
Publisher: Woodhead Publishing
ISBN: 008102651X
Category : Business & Economics
Languages : en
Pages : 672
Book Description
Advances in Nuclear Fuel Chemistry presents a high-level description of nuclear fuel chemistry based on the most recent research and advances. Dr. Markus H.A. Piro and his team of global, expert contributors cover all aspects of both the conventional uranium-based nuclear fuel cycle and non-conventional fuel cycles, including mining, refining, fabrication, and long-term storage, as well as emerging nuclear technologies, such as accident tolerant fuels and molten salt materials. Aimed at graduate students, researchers, academics and practicing engineers and regulators, this book will provide the reader with a single reference from which to learn the fundamentals of classical thermodynamics and radiochemistry. Consolidates the latest research on nuclear fuel chemistry into one comprehensive reference, covering all aspects of traditional and non-traditional nuclear fuel cycles Includes contributions from world-renowned experts from many countries representing government, industry and academia Covers a variety of fuel designs, including conventional uranium dioxide, mixed oxides, research reactor fuels, and molten salt fuels Written by experts with hands-on experience in the development of such designs
Publisher: Woodhead Publishing
ISBN: 008102651X
Category : Business & Economics
Languages : en
Pages : 672
Book Description
Advances in Nuclear Fuel Chemistry presents a high-level description of nuclear fuel chemistry based on the most recent research and advances. Dr. Markus H.A. Piro and his team of global, expert contributors cover all aspects of both the conventional uranium-based nuclear fuel cycle and non-conventional fuel cycles, including mining, refining, fabrication, and long-term storage, as well as emerging nuclear technologies, such as accident tolerant fuels and molten salt materials. Aimed at graduate students, researchers, academics and practicing engineers and regulators, this book will provide the reader with a single reference from which to learn the fundamentals of classical thermodynamics and radiochemistry. Consolidates the latest research on nuclear fuel chemistry into one comprehensive reference, covering all aspects of traditional and non-traditional nuclear fuel cycles Includes contributions from world-renowned experts from many countries representing government, industry and academia Covers a variety of fuel designs, including conventional uranium dioxide, mixed oxides, research reactor fuels, and molten salt fuels Written by experts with hands-on experience in the development of such designs
Semiannual Report of the Atomic Energy Commission
Author: U.S. Atomic Energy Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 926
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 926
Book Description