Development Of A Core Design Optimization Tool And Analysis In Support Of The Planned Low Enriched Uranium Conversion Of The Mit Research Reactor Mitr Ii

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Development of a Core Design Optimization Tool and Analysis in Support of the Planned Low Enriched Uranium Conversion of the MIT Research Reactor (MITR-II)

Author : Heather Moira Connaway
Publisher :
ISBN 13 :
Total Pages : 185 pages
Book Rating : 4.:/5 (841 download)

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Book Synopsis Development of a Core Design Optimization Tool and Analysis in Support of the Planned Low Enriched Uranium Conversion of the MIT Research Reactor (MITR-II) by : Heather Moira Connaway

Download or read book Development of a Core Design Optimization Tool and Analysis in Support of the Planned Low Enriched Uranium Conversion of the MIT Research Reactor (MITR-II) written by Heather Moira Connaway and published by . This book was released on 2012 with total page 185 pages. Available in PDF, EPUB and Kindle. Book excerpt: The MIT Research Reactor (MITR-II) is currently undergoing analysis for the planned conversion from high enriched uranium (HEU) to low enriched uranium (LEU), as part of a global effort to minimize the availability of weapons-grade uranium. In support of efficient fuel management analysis with the new LEU fuel, a core design optimization tool has been developed. Using a coarse model, the tool can quickly consider the large range of refueling options available, and identify a solution which minimizes power peaking with the least fuel shuffling possible. The selected scheme can then be examined in greater detail with a more robust simulation tool. The unique geometry of the MITR core makes it difficult to develop a model that both runs very quickly and provides detailed power distribution information. Therefore, a correlation-based approach has been employed. Relationships between burnup, critical control blade position, core Um mass, and power distribution are used to predict fuel element U235 depletion, critical control blade motion, and power peaking. The tool applies the correlations to identify an optimal loading pattern, defined as the core which has the lowest maximum radial peaking factor in the set of valid solutions with the minimum number of fuel shuffling actions. The correlations that are utilized by the optimization tool were developed using data from simulations with MCODE-FM, a fuel management wrapper for the MCNP-ORIGEN linkage code MCODE. The correlations have been verified with results from additional MCODE-FM runs, and the code logic has been verified with the core loading solutions for a variety of input parameters. The verification found that the code is able to predict radial peaking, core mass, and general control blade motion with sufficient accuracy to develop a good refueling scheme. The tool provides the output solution in an interactive format, which allows the user to quickly examine small perturbations on the identified loading pattern. In addition to the optimization tool development, loading patterns for the mixed HEU-LEU fuel transition cores have been evaluated. This analysis identified general behavioral trends of the mixed-fuel cores, which serve as an initial basis for future transition core analysis.

Expanding and Optimizing Fuel Management and Data Analysis Capabilities of MCODE-FM in Support of Massachusetts Institute of Technology Research Reactor (MITR-II) LEU Conversion

Download Expanding and Optimizing Fuel Management and Data Analysis Capabilities of MCODE-FM in Support of Massachusetts Institute of Technology Research Reactor (MITR-II) LEU Conversion PDF Online Free

Author : Nicholas Edward Horelik
Publisher :
ISBN 13 :
Total Pages : 343 pages
Book Rating : 4.:/5 (823 download)

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Book Synopsis Expanding and Optimizing Fuel Management and Data Analysis Capabilities of MCODE-FM in Support of Massachusetts Institute of Technology Research Reactor (MITR-II) LEU Conversion by : Nicholas Edward Horelik

Download or read book Expanding and Optimizing Fuel Management and Data Analysis Capabilities of MCODE-FM in Support of Massachusetts Institute of Technology Research Reactor (MITR-II) LEU Conversion written by Nicholas Edward Horelik and published by . This book was released on 2012 with total page 343 pages. Available in PDF, EPUB and Kindle. Book excerpt: Studies are underway in support of the MIT research reactor (MITR-II) conversion from high enriched Uranium (HEU) to low enriched Uranium (LEU), as required by recent non-proliferation policy. With the same core configuration and similar assembly type, high-density monolithic U-Mo fuel will replace the current HEU fuel with comparable performance. Part of the required analysis for relicensing includes detailed fuel management and burnup studies with the new LEU fuel, to be carried out with a recently developed fuel management tool called MCODE-FM. This code-package is a Python wrapper enabling automatic fuel shuffling between successive runs of MIT's MCODE, which couples MCNP with ORIGEN for full-core neutronics and depletion. In this work, the capabilities of MCODE have been expanded, and the effects of depletion mesh parameters have been explored. Several features have been added to the fuel management tool to encompass the the full range of fuel management options needed for detailed analysis, including assembly flipping, rotation, and temporary storage above the core. In addition, an option to easily manage experiments and custom dummy elements has been added, and a parallel version of MCODE for MCODE-FM that better handles finer discretizations of full-core runs has been developed. These changes have been made in the main wrapper utility as well as the graphical user interface (GUI). In addition to the new MCODE-FM capabilities, a suite of automatic data analysis utilities were developed to consistently parse results. These include utilities to extract or calculate isotope data, fission powers, blade heights, peaking factors, and 3D VTK files for visualization at any time step. The suite has been developed as a series of Python scripts, accessible also through the MCODE-FM GUI. Finally, the effects of the spatial discretization parameters for the depletion mesh have been explored, and mesh choice recommendations have been made for different types of studies. In summary, coarser meshes in the radial and lateral dimensions have been found to yield conservative power peaking results, whereas a finer axial mesh is needed axially. Thus for iterative fuel management studies a fast-running depletion mesh of 8 axial regions, 3 radial regions, and 1 lateral region can be used. However, for safety studies and benchmarking that only need to run once or twice, 16 axial regions, 15 or 18 radial regions (HEU or LEU, respectively), and 4 lateral regions should be used.

Impact Assessment for the MIT Research Reactor Low Enrichment Uranium Fuel Fabrication Tolerances

Author : Dakota J. Allen
Publisher :
ISBN 13 :
Total Pages : 109 pages
Book Rating : 4.:/5 (119 download)

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Book Synopsis Impact Assessment for the MIT Research Reactor Low Enrichment Uranium Fuel Fabrication Tolerances by : Dakota J. Allen

Download or read book Impact Assessment for the MIT Research Reactor Low Enrichment Uranium Fuel Fabrication Tolerances written by Dakota J. Allen and published by . This book was released on 2020 with total page 109 pages. Available in PDF, EPUB and Kindle. Book excerpt: In the framework of non-proliferation policy, the Massachusetts Institute of Technology Reactor (MITR) is planning to convert from highly enriched uranium (HEU) to low enriched uranium (LEU) fuel. A new type of high-density LEU fuel based on a monolithic U-10Mo alloy is being qualified to allow the conversion of all remaining U.S. high performance research reactors including the MITR. The purpose of this study is to understand the impact of proposed MITR LEU "FYT" fuel element fabrication tolerances on the operation and safety limits of the MITR. Therefore, the effects of fabrication specification parameters on all levels of the core, ranging from full-core alterations to individual spots on the fuel plates were analyzed. Evaluations at the design tolerances, and beyond, were conducted through neutronics and thermal hydraulics calculations. The first step was analyzing the separate effects that parameters, including enrichment, fuel mass loading, fuel plate thickness, and impurities, have on the reactor physics of the core. These analyses were used to develop curve fits to predict the effect of these parameters on the excess reactivity of fresh fuel inserted into the LEU core. These models could then be used to estimate the effect on fuel cycle length to ensure the tolerances would not cause significant changes to the operating cycle of MITR. These analyses estimated the margin to criticality present in the core and ensured that the reactivity shutdown margin (SDM) was not violated. Other parameters such as coolant channel gap and local fuel homogeneity cause primarily local impacts including the power distribution within the fuel element, and related impacts to thermal hydraulic margins. This modeling was necessary to ensure that these parameters would not cause the margin to MITR's thermal hydraulic safety limit, the onset of nucleate boiling (ONB), to be violated. The final step was a covariance analysis of the combined effects at a full-core and element level. This combined effect analysis assured that the core would maintain proper safety and operational margins with a realistic distribution of off-nominal parameters. Given the comprehensive analysis performed, the current design fabrication tolerances were determined to provide acceptable fuel cycle length and safety margins consistent with the MITR LEU preliminary safety analysis report, and a basis for updating these tolerances during planned manufacturing-scale plate fabrication demonstrations has been established.

A Source-sink Calculation of the MIT Research Reactor

Author : Martin B. Cutrone
Publisher :
ISBN 13 :
Total Pages : 178 pages
Book Rating : 4.:/5 (327 download)

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Book Synopsis A Source-sink Calculation of the MIT Research Reactor by : Martin B. Cutrone

Download or read book A Source-sink Calculation of the MIT Research Reactor written by Martin B. Cutrone and published by . This book was released on 1960 with total page 178 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Research and Development of Multiphysics Models in Support of the Conversion of the High Flux Isotope Reactor to Low Enriched Uranium Fuel

Download Research and Development of Multiphysics Models in Support of the Conversion of the High Flux Isotope Reactor to Low Enriched Uranium Fuel PDF Online Free

Author :
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (962 download)

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Book Synopsis Research and Development of Multiphysics Models in Support of the Conversion of the High Flux Isotope Reactor to Low Enriched Uranium Fuel by :

Download or read book Research and Development of Multiphysics Models in Support of the Conversion of the High Flux Isotope Reactor to Low Enriched Uranium Fuel written by and published by . This book was released on 2015 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: ABSTRACT The findings presented in this report are results of a five year effort lead by the RRD Division of the ORNL, which is focused on research and development toward the conversion of the High Flux Isotope Reactor (HFIR) fuel from high-enriched uranium (HEU) to low-enriched uranium (LEU). This report focuses on the tasks accomplished by the University of Tennessee Knoxville (UTK) team from the Department of Mechanical, Aerospace, and Biomedical Engineering (MABE) that provided expert support in multiphysics modeling of complex problems associated with the LEU conversion of the HFIR reactor. The COMSOL software was used as the main computational modeling tool, whereas Solidworks was also used in support of computer-aided-design (CAD) modeling of the proposed LEU fuel design. The UTK research has been governed by a statement of work (SOW), which was updated annually to clearly define the specific tasks reported herein. Ph. D. student Isaac T. Bodey has focused on heat transfer and fluid flow modeling issues and has been aided by his major professor Dr. Rao V. Arimilli. Ph. D. student Franklin G. Curtis has been focusing on modeling the fluid-structure interaction (FSI) phenomena caused by the mechanical forces acting on the fuel plates, which in turn affect the fluid flow in between the fuel plates, and ultimately the heat transfer, is also affected by the FSI changes. Franklin Curtis has been aided by his major professor Dr. Kivanc Ekici. M. Sc. student Adam R. Travis has focused two major areas of research: (1) on accurate CAD modeling of the proposed LEU plate design, and (2) reduction of the model complexity and dimensionality through interdimensional coupling of the fluid flow and heat transfer for the HFIR plate geometry. Adam Travis is also aided by his major professor, Dr. Kivanc Ekici. We must note that the UTK team, and particularly the graduate students, have been in very close collaboration with Dr. James D. Freels (ORNL technical monitor and mentor) and have benefited greatly from his leadership and expertise in COMSOL modeling of complex physical phenomena. Both UTK and ORNL teams have used COMSOL releases 3.4 through 5.0 inclusive (with particular emphasis on 3.5a, 4.3a, 4.3b, and 4.4) for most of the work described in this report, except where stated otherwise. Just as in the performance of the research, each of the respective sections has been originally authored by respective authors. Therefore, the reader will observe a contrast in writing style throughout this document.

Development of CFD Models to Support LEU Conversion of ORNL S High Flux Isotope Reactor

Author :
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (16 download)

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Book Synopsis Development of CFD Models to Support LEU Conversion of ORNL S High Flux Isotope Reactor by :

Download or read book Development of CFD Models to Support LEU Conversion of ORNL S High Flux Isotope Reactor written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The US Department of Energy s National Nuclear Security Administration (NNSA) is participating in the Global Threat Reduction Initiative to reduce and protect vulnerable nuclear and radiological materials located at civilian sites worldwide. As an integral part of one of NNSA s subprograms, Reduced Enrichment for Research and Test Reactors, HFIR is being converted from the present HEU core to a low enriched uranium (LEU) core with less than 20% of U-235 by weight. Because of HFIR s importance for condensed matter research in the United States, its conversion to a high-density, U-Mo-based, LEU fuel should not significantly impact its existing performance. Furthermore, cost and availability considerations suggest making only minimal changes to the overall HFIR facility. Therefore, the goal of this conversion program is only to substitute LEU for the fuel type in the existing fuel plate design, retaining the same number of fuel plates, with the same physical dimensions, as in the current HFIR HEU core. Because LEU-specific testing and experiments will be limited, COMSOL Multiphysics was chosen to provide the needed simulation capability to validate against the HEU design data and previous calculations, and predict the performance of the proposed LEU fuel for design and safety analyses. To achieve it, advanced COMSOL-based multiphysics simulations, including computational fluid dynamics (CFD), are being developed to capture the turbulent flows and associated heat transfer in fine detail and to improve predictive accuracy [2].

Analyzing how Optimization Features Impact People's Use of Design Tools

Author : Elizabeth H. W. Gaylord
Publisher :
ISBN 13 :
Total Pages : 22 pages
Book Rating : 4.:/5 (18 download)

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Book Synopsis Analyzing how Optimization Features Impact People's Use of Design Tools by : Elizabeth H. W. Gaylord

Download or read book Analyzing how Optimization Features Impact People's Use of Design Tools written by Elizabeth H. W. Gaylord and published by . This book was released on 2018 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt: Design is the first step in creating a product but can be the most challenging. Much design software has been created to meet these needs, but these tools consider only a small part of the design process. This limitation stunts creativity and provides challenges to designers when trying to solve complex problems. Better tools take into account the needs of designers throughout the process of creating, analyzing, and optimizing designs. To provide the best integrated solutions, it is necessary to determine what features of analysis and optimization most help designers explore the solution space and ultimately create better physical designs. Tacit was developed as research tool to create simple designs with analysis and optimization built-in to the software. The most optimized version of Tacit was used as the control in a new study, which utilized two new versions excluding certain optimization features. A comparison between these versions was done to examine how optimization features impacted overall result, solution space exploration, and user experience. The usefulness of these optimization features is highly dependent on the type of problem being solved, and these features do not guarantee the best solution or sufficient exploration of the design space. Results from this experiment allow researchers to identify what is most useful to designers and how better to design tools to help them.

Research Reactor Core Conversion Guidebook. Vol. 2

Author : International Atomic Energy Agency, Vienna (Austria).
Publisher :
ISBN 13 :
Total Pages : 386 pages
Book Rating : 4.:/5 (476 download)

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Book Synopsis Research Reactor Core Conversion Guidebook. Vol. 2 by : International Atomic Energy Agency, Vienna (Austria).

Download or read book Research Reactor Core Conversion Guidebook. Vol. 2 written by International Atomic Energy Agency, Vienna (Austria). and published by . This book was released on 1992 with total page 386 pages. Available in PDF, EPUB and Kindle. Book excerpt:

MCODE-3

Author : Thomas P. Gerrity (III.)
Publisher :
ISBN 13 :
Total Pages : 72 pages
Book Rating : 4.:/5 (824 download)

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Book Synopsis MCODE-3 by : Thomas P. Gerrity (III.)

Download or read book MCODE-3 written by Thomas P. Gerrity (III.) and published by . This book was released on 2012 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt: In order to operate a reactor safely and efficiently, computer simulations must be used to predict certain nuclear characteristics of the reactor. To determine how materials change in a fission power environment, a time-dependent depletion isotopic code must be used. Over the past several decades, the MIT Reactor (MITR) has taken many steps to prepare for its conversion from the use of highly enriched uranium (HEU) to low enriched uranium (LEU) in its fuel. Throughout this process, detailed neutronics simulations must be run to predict the characteristics of the reactor with its current HEU fuel, with potential forms of LEU fuel, and with combinations of the two. MCODE Version 3 is a linkage code that performs time-dependent burnup calculations by combining the Monte Carlo N-Particle transport code, MCNP, with the Oak Ridge Isotope Generation point depletion code, ORIGEN-S. MCNP provides reaction rates and neutron flux in user-specified irradiation material regions. COUPLE, a data-editing code included in the SCALE- 6.1 software package, uses these data from MCNP to update the cross section libraries, which ORIGEN then uses to perform nuclide depletion calculations in each irradiation zone. The MCNP model is then updated with the depleted material compositions, and the exchange is repeated. The MCNP/ORIGEN coupling utilizes an optional predictor-corrector capability. As a newer version of MCODE Version 2.2, MCODE-3 offers three major changes from its predecessor. The first is the incorporation of ORIGEN-S. MCODE-2 used a previous version of ORIGEN, which is no longer supported by ORNL. ORIGEN-S provides newer nuclear data as well as additional functionality and usability. Secondly, MCODE-3 uses COUPLE to create an entirely unique cross section library from the regionally averaged 238-group flux, which means every cross section value that MCODE-3 uses in its depletion is specific to the input model. MCODE-2 only updates a fraction of nuclides' cross sections, the rest default to a pre-compiled library. Finally, while MCODE-2.2 was written in ANSI C, MCODE-3's main function has been rewritten in the Python scripting language. MCODE's preproc, mcodeout, and mcnpxs programs have not been edited, and are thus still written in ANSI C. Benchmarking has indicated that while the evolution of most nuclides is similar to an MCODE-2 calculation, over many depletion steps some nuclides can diverge due to COUPLE's use of the 238-group flux.

Osiris

Author :
Publisher :
ISBN 13 :
Total Pages : 10 pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis Osiris by :

Download or read book Osiris written by and published by . This book was released on 2007 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: To meet the simulation needs of the GNEP program, LLNL is leveraging a suite of high-performance codes to be used in the development of a multi-physics tool for modeling nuclear reactor cores. The Osiris code project, which began last summer, is employing modern computational science techniques in the development of the individual physics modules and the coupling framework. Initial development is focused on coupling thermal-hydraulics and neutral-particle transport, while later phases of the project will add thermal-structural mechanics and isotope depletion. Osiris will be applicable to the design of existing and future reactor systems through the use of first-principles, coupled physics models with fine-scale spatial resolution in three dimensions and fine-scale particle-energy resolution. Our intent is to replace an existing set of legacy, serial codes which require significant approximations and assumptions, with an integrated, coupled code that permits the design of a reactor core using a first-principles physics approach on a wide range of computing platforms, including the world's most powerful parallel computers. A key research activity of this effort deals with the efficient and scalable coupling of physics modules which utilize rather disparate mesh topologies. Our approach allows each code module to use a mesh topology and resolution that is optimal for the physics being solved, and employs a mesh-mapping and data-transfer module to effect the coupling. Additional research is planned in the area of scalable, parallel thermal-hydraulics, high-spatial-accuracy depletion and coupled-physics simulation using Monte Carlo transport.

Utilization Related Design Features of Research Reactors

Author : International Atomic Energy Agency
Publisher :
ISBN 13 : 9781523129898
Total Pages : 0 pages
Book Rating : 4.1/5 (298 download)

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Book Synopsis Utilization Related Design Features of Research Reactors by : International Atomic Energy Agency

Download or read book Utilization Related Design Features of Research Reactors written by International Atomic Energy Agency and published by . This book was released on 2009 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: For more than 50 years research reactors have played an important role in the development of nuclear science and technology. They have made significant contributions to a large number of disciplines, as well as to the educational and research programmes of about 70 countries worldwide. There are substantial utilization issues being faced by the research reactor community, including the selection, design and operation of various types of devices in research reactors. This publication has been prepared by the IAEA to facilitate the exchange of ideas, concepts and experience. It presents descriptions of design and utilization features of facilities and associated devices that are implemented in different research reactors worldwide, covering selected fields of application.

Guide to Nuclear Power Cost Evaluation: Equipment costs

Author : Kaiser Engineers
Publisher :
ISBN 13 :
Total Pages : 140 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Guide to Nuclear Power Cost Evaluation: Equipment costs by : Kaiser Engineers

Download or read book Guide to Nuclear Power Cost Evaluation: Equipment costs written by Kaiser Engineers and published by . This book was released on 1962 with total page 140 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Molybdenum-99 for Medical Imaging

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)

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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.

The United Nations World Water Development Report – N° 5 - 2014

Author : UNESCO
Publisher : UNESCO
ISBN 13 : 9231042599
Total Pages : 230 pages
Book Rating : 4.2/5 (31 download)

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Book Synopsis The United Nations World Water Development Report – N° 5 - 2014 by : UNESCO

Download or read book The United Nations World Water Development Report – N° 5 - 2014 written by UNESCO and published by UNESCO. This book was released on 2014-03-21 with total page 230 pages. Available in PDF, EPUB and Kindle. Book excerpt: The WWDR 2014 on Water and Energy is now an annual and thematic report with a focus on different strategic water issues each year. It is shorter in the order of 100 pages with a standardized structure and data and case studies annexes related to the theme. The WWDR 2014 will be launched during the main World Water Day celebrations in Tokyo, Japan on 21 March 2014. Water and energy are closely interconnected and highly interdependent. Trade-offs need to be managed to limit negative impacts and foster opportunities for synergy. Water and energy have crucial impacts on poverty alleviation both directly, as a number of the Millennium Development Goals depend on major improvements in access to water, sanitation, power and energy sources, and indirectly, as water and energy can be binding constraints on economic growth the ultimate hope for widespread poverty reduction. This fifth edition of the United Nations World Water Development Report (WWDR 2014) seeks to inform decision-makers

NUREG/CR.

Author : U.S. Nuclear Regulatory Commission
Publisher :
ISBN 13 :
Total Pages : 48 pages
Book Rating : 4.:/5 (319 download)

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Book Synopsis NUREG/CR. by : U.S. Nuclear Regulatory Commission

Download or read book NUREG/CR. written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1977 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Reactor Core Materials

Author :
Publisher :
ISBN 13 :
Total Pages : 304 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Reactor Core Materials by :

Download or read book Reactor Core Materials written by and published by . This book was released on 1960 with total page 304 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Nuclear Batteries and Radioisotopes

Author : Mark Prelas
Publisher : Springer
ISBN 13 : 331941724X
Total Pages : 363 pages
Book Rating : 4.3/5 (194 download)

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Book Synopsis Nuclear Batteries and Radioisotopes by : Mark Prelas

Download or read book Nuclear Batteries and Radioisotopes written by Mark Prelas and published by Springer. This book was released on 2016-08-04 with total page 363 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book explains the physics of nuclear battery operation. It provides a comprehensive background that allows readers to understand all past and future developments in the field. The supply and cost of radioisotopes for use in applications (focused on nuclear batteries) are covered in the initial sections of the text. The interaction of ionizing radiation with matter is discussed as applied to nuclear batteries. The physics of interfacing the radioisotopes to the transducers which represent the energy conversion mechanism for nuclear batteries are described for possible nuclear battery configurations. Last but not least the efficiencies of nuclear battery configurations are discussed combined with a review of the literature on nuclear battery research.