Production and Measurement of Minor Actinides in the Commercial Fuel Cycle

Production and Measurement of Minor Actinides in the Commercial Fuel Cycle

Author:

Publisher:

Published: 1997

Total Pages: 29

ISBN-13:

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The minor actinide elements, particularly neptunium and americium, are produced as a normal byproduct of the operation of thermal power reactors. Because of the existence of long-lived isotopes of these elements, they constitute the major sources of the residual radiation in spent fuel or in wastes resulting from reprocessing. This has led to examinations by some countries of the possibility of separating the minor actinides from waste products. The papers found in this report address the production of minor actinides in common thermal power reactors as well as approaches to measure these materials in various media. The first paper in this volume, {open_quotes}Production of Minor Actinides in the Commercial Fuel Cycle, {close_quotes} uses calculations with the ORIGEN2 reactor and decay code to estimate the amounts of minor actinides in spent fuel and separated plutonium as a function of reactor irradiation and the time after discharge. The second paper, {open_quotes}Destructive Assay of Minor Actinides, {close_quotes} describes a number of promising approaches for the chemical analysis of minor actinides in the various forms in which they are found at reprocessing plants. The next paper, {open_quotes}Hybrid KED/XRF Measurement of Minor Actinides in Reprocessing Plants, {close_quotes} uses the results of a simulation model to examine the possible applications of the hybrid KED/XRF instrument to the determination of minor actinides in some of the solutions found in reprocessing plants. In {open_quotes}Calorimetric Assay of Minor Actinides, {close_quotes} the authors show some possible extensions of this powerful technique beyond the normal plutonium assays to include the minor actinides. Finally, the last paper in this volume, {open_quotes}Environment Measurements of Transuranic Nuclides, {close_quotes} discusses what is known about the levels of the minor actinides in the environment and ways to analyze for these materials in environmental matrices.


Measurement and Accounting of the Minor Actinides Produced in Nuclear Power Reactors

Measurement and Accounting of the Minor Actinides Produced in Nuclear Power Reactors

Author:

Publisher:

Published: 1996

Total Pages: 27

ISBN-13:

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Because of their value as nuclear fuels and their impact on long-term storage of high-level radioactive waste, measurement and accounting for minor actinides (MAs) produced in nuclear power reactors are becoming significant issues. This report attempts to put the issues in perspective by reviewing the commercial nuclear fuel cycle with emphasis on reprocessing plants and key measurement points therein. Radiation signatures and characteristics are compared and contrasted for special nuclear materials (SNMs) and MAs. Also, inventories and relative amounts of SNMs and MAs are generally described for irradiated nuclear fuel and reprocessing plants. The bulk of the report describes appropriate measurement technologies, capabilities, and development needs to satisfy material accounting requirements for MAs, with emphasis on adaptation of current technologies. Recommendations for future systems studies and development of measurement methods are also included. 38 refs., 3 figs., 12 tabs.


Production of Minor Actinides in the Commercial Fuel Cycle

Production of Minor Actinides in the Commercial Fuel Cycle

Author:

Publisher:

Published: 1996

Total Pages: 8

ISBN-13:

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The minor actinides are an inevitable by-product of the production of electricity with thermal reactors. This paper will review the mechanisms of production of the principal minor actinides (237Np, 241Am, and 243Am) and their expected concentrations in spent fuel from commercial power reactors as well as in Pu produced from reprocessing these types of spent fuels. All the results shown are derived from calculations done using the ORIGEN2 reactor code.


Neutron-based Measurements for Nondestructive Assay of Minor Actinides Produced in Nuclear Power Reactors

Neutron-based Measurements for Nondestructive Assay of Minor Actinides Produced in Nuclear Power Reactors

Author:

Publisher:

Published: 1996

Total Pages: 16

ISBN-13:

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Because of their impacts on long-term storage of high-level radioactive waste and their value as nuclear fuels, measurement and accounting of the minor actinides produced in nuclear power reactors are becoming significant issues. This paper briefly reviews the commercial nuclear fuel cycle with emphasis on reprocessing plants and key measurement points therein. Neutron signatures and characteristics are compared and contrasted for special nuclear materials (SNMs) and minor actinides (MAs). The paper focuses on application of neutron-based nondestructive analysis (NDA) methods that can be extended for verification of MAs. We describe current IAEA methods for NDA of SNMs and extension of these methods to satisfy accounting requirements for MAs in reprocessing plant dissolver solutions, separated products, and high-level waste. Recommendations for further systems studies and development of measurement methods are also included.


Recent Advances In Actinide Science

Recent Advances In Actinide Science

Author: Iain May

Publisher: Royal Society of Chemistry

Published: 2007-10-31

Total Pages: 831

ISBN-13: 1847555365

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Actinide elements and their chemistry have a significant number of applications. Bringing together contributions from the leading experts in the field, Recent Advances in Actinide Science covers six main topics: * Analysis, the environment and biotransformations * Coordination and organometallic chemistry * Heavy elements * Nuclear fuels, materials and waste forms * Separations and solution chemistry * Spectroscopy, magnetism and superconductivity Covering a wide range of research from pure academic studies to applied industrial science and technology, this book distils the knowledge and achievements gained in actinide science over the last four years. This high level book is aimed at researchers, both industrial and academic, and provides a comprehensive overview of the current status of actinide science.


Status of Minor Actinide Fuel Development

Status of Minor Actinide Fuel Development

Author: H. P. Nawada

Publisher:

Published: 2009

Total Pages: 81

ISBN-13: 9789201069092

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This publication's main objective is to respond to the growing interest of Member States in the development of advanced and innovative technologies for safe, proliferation resistant and economically efficient nuclear fuel cycles, while minimising waste and environmental impacts. It includes detailed analyses of ongoing research and development activities related to the developmental status of minor actinides containing fuels and targets and its transmutation, reviews reactor and fuel cycle options and discusses performance characteristics of various minor actinide bearing fuel types, and summarises the results of irradiation tests on minor actinide fuels. The comprehensive information compiled in this book and on the accompanying CD-ROM will be a valuable resource for scientists, engineers and designers involved in the development of advanced nuclear fuels with actinide recycling.


Nuclear Fuel Cycle Simulation System (VISTA)

Nuclear Fuel Cycle Simulation System (VISTA)

Author: International Atomic Energy Agency

Publisher: IAEA

Published: 2007

Total Pages: 112

ISBN-13:

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The Nuclear Fuel Cycle Simulation System (VISTA) is a simulation system which estimates long term nuclear fuel cycle material and service requirements as well as the material arising from the operation of nuclear fuel cycle facilities and nuclear power reactors. It is a scenario based simulation tool which can model several nuclear fuel cycle options including existing nuclear power reactor types and future possible reactor types. The past operations of the power reactors and fuel cycle facilities can be modelled in the system, in order to estimate the current amount of spent fuel stored or total Pu in stored spent fuel. It can also accept future projections for nuclear power and other scenario parameters in order to predict future fuel cycle material requirements.The model has been designed to be an optimum mixture of simplicity, speed and accuracy. It does not require too many input parameters if the purpose is just to compare the requirements for selected scenarios. Furthermore, the accuracy of the system can be improved by introducing more detailed and correct sets of input parameters.


Disposition of High-Level Waste and Spent Nuclear Fuel

Disposition of High-Level Waste and Spent Nuclear Fuel

Author: National Research Council

Publisher: National Academies Press

Published: 2001-07-05

Total Pages: 215

ISBN-13: 0309073170

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Focused attention by world leaders is needed to address the substantial challenges posed by disposal of spent nuclear fuel from reactors and high-level radioactive waste from processing such fuel. The biggest challenges in achieving safe and secure storage and permanent waste disposal are societal, although technical challenges remain. Disposition of radioactive wastes in a deep geological repository is a sound approach as long as it progresses through a stepwise decision-making process that takes advantage of technical advances, public participation, and international cooperation. Written for concerned citizens as well as policymakers, this book was sponsored by the U.S. Department of Energy, U.S. Nuclear Regulatory Commission, and waste management organizations in eight other countries.


Behavior of Actinides in the Integral Fast Reactor Fuel Cycle

Behavior of Actinides in the Integral Fast Reactor Fuel Cycle

Author:

Publisher:

Published: 1994

Total Pages: 14

ISBN-13:

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The Integral Fast Reactor (IFR) under development by Argonne National Laboratory uses metallic fuels instead of ceramics. This allows electrorefining of spent fuels and presents opportunities for recycling minor actinide elements. Four minor actinides (237Np, 24°Pu, 241Am, and 243Am) determine the waste storage requirements of spent fuel from all types of fission reactors. These nuclides behave the same as uranium and other plutonium isotopes in electrorefining, so they can be recycled back to the reactor without elaborate chemical processing. An experiment has been designed to demonstrate the effectiveness of the high-energy neutron spectra of the IFR in consuming these four nuclides and plutonium. Eighteen sets of seven actinide and five light metal targets have been selected for ten day exposure in the Experimental Breeder Reactor-2 which serves as a prototype of the IFR. Post-irradiation analyses of the exposed targets by gamma, alpha, and mass spectroscopy are used to determine nuclear reaction-rates and neutron spectra. These experimental data increase the authors' confidence in their ability to predict reaction rates in candidate IFR designs using a variety of neutron transport and diffusion programs.