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Author : James S. Tulenko
Release : 2005
Genre : Plutonium
Kind : eBook
Book Rating : /5 ( reviews)
Book Synopsis The Optimum Plutonium Inert Matrix Fuel Form for Reactor-based Plutonium Disposition by : James S. Tulenko
Download or read book The Optimum Plutonium Inert Matrix Fuel Form for Reactor-based Plutonium Disposition written by James S. Tulenko. This book was released on 2005. Available in PDF, EPUB and Kindle. Book excerpt:
Author : J. Wang
Release : 2004
Genre :
Kind : eBook
Book Rating : /5 ( reviews)
Book Synopsis The Optimum Plutonium Inert Matrix Fuel Form for Reactor-Based Plutonium Disposition by : J. Wang
Download or read book The Optimum Plutonium Inert Matrix Fuel Form for Reactor-Based Plutonium Disposition written by J. Wang. This book was released on 2004. Available in PDF, EPUB and Kindle. Book excerpt: The University of Florida has underway an ongoing research program to validate the economic, operational and performance benefits of developing an inert matrix fuel (IMF) for the disposition of the U.S. weapons plutonium (Pu) and for the recycle of reprocessed Pu. The current fuel form of choice for Pu disposition for the Department of Energy is as a mixed oxide (MOX) (PuO2/UO2). We will show analyses that demonstrate that a Silicon Carbide (SiC) IMF offers improved performance capabilities as a fuel form for Pu recycle and disposition. The reason that UF is reviewing various materials to serve as an inert matrix fuel is that an IMF fuel form can offer greatly reduced Pu and transuranic isotope (TRU) production and also improved thermal performance characteristics. Our studies showed that the Pu content is reduced by an order of magnitude while centerline fuel temperatures are reduced approximately 380 degrees centigrade compared to MOX. These reduced temperatures result in reduced stored heat and thermal stresses in the pellet. The reduced stored heat reduces the consequences of the loss of coolant accident, while the reduced temperatures and thermal stresses yield greatly improved fuel performance. Silicon Carbide is not new to the nuclear industry, being a basic fuel material in gas cooled reactors.
Author :
Release : 2004
Genre :
Kind : eBook
Book Rating : /5 ( reviews)
Book Synopsis The Optimum Plutonium Inert Matrix Fuel Form for Reactor-Based Plutonium Disposition by :
Download or read book The Optimum Plutonium Inert Matrix Fuel Form for Reactor-Based Plutonium Disposition written by . This book was released on 2004. Available in PDF, EPUB and Kindle. Book excerpt: The University of Florida has underway an ongoing research program to validate the economic, operational and performance benefits of developing an inert matrix fuel (IMF) for the disposition of the U.S. weapons plutonium (Pu) and for the recycle of reprocessed Pu. The current fuel form of choice for Pu disposition for the Department of Energy is as a mixed oxide (MOX) (PuO2/UO2). We will show analyses that demonstrate that a Silicon Carbide (SiC) IMF offers improved performance capabilities as a fuel form for Pu recycle and disposition. The reason that UF is reviewing various materials to serve as an inert matrix fuel is that an IMF fuel form can offer greatly reduced Pu and transuranic isotope (TRU) production and also improved thermal performance characteristics. Our studies showed that the Pu content is reduced by an order of magnitude while centerline fuel temperatures are reduced approximately 380 degrees centigrade compared to MOX. These reduced temperatures result in reduced stored heat and thermal stresses in the pellet. The reduced stored heat reduces the consequences of the loss of coolant accident, while the reduced temperatures and thermal stresses yield greatly improved fuel performance. Silicon Carbide is not new to the nuclear industry, being a basic fuel material in gas cooled reactors.
Author :
Release : 1999
Genre :
Kind : eBook
Book Rating : /5 ( reviews)
Book Synopsis Physics and Fuel Performance of Reactor-Based Plutonium Disposition by :
Download or read book Physics and Fuel Performance of Reactor-Based Plutonium Disposition written by . This book was released on 1999. Available in PDF, EPUB and Kindle. Book excerpt:
Author : National Research Council
Release : 2003-06-09
Genre : Science
Kind : eBook
Book Rating : 228/5 ( reviews)
Book Synopsis Improving the Scientific Basis for Managing DOE's Excess Nuclear Materials and Spent Nuclear Fuel by : National Research Council
Download or read book Improving the Scientific Basis for Managing DOE's Excess Nuclear Materials and Spent Nuclear Fuel written by National Research Council. This book was released on 2003-06-09. Available in PDF, EPUB and Kindle. Book excerpt: The production of nuclear materials for the national defense was an intense, nationwide effort that began with the Manhattan Project and continued throughout the Cold War. Now many of these product materials, by-products, and precursors, such as irradiated nuclear fuels and targets, have been declared as excess by the Department of Energy (DOE). Most of this excess inventory has been, or will be, turned over to DOE's Office of Environmental Management (EM), which is responsible for cleaning up the former production sites. Recognizing the scientific and technical challenges facing EM, Congress in 1995 established the EM Science Program (EMSP) to develop and fund directed, long-term research that could substantially enhance the knowledge base available for new cleanup technologies and decision making. The EMSP has previously asked the National Academies' National Research Council for advice for developing research agendas in subsurface contamination, facility deactivation and decommissioning, high-level waste, and mixed and transuranic waste. For this study the committee was tasked to provide recommendations for a research agenda to improve the scientific basis for DOE's management of its high-cost, high-volume, or high-risk excess nuclear materials and spent nuclear fuels. To address its task, the committee focused its attention on DOE's excess plutonium-239, spent nuclear fuels, cesium-137 and strontium-90 capsules, depleted uranium, and higher actinide isotopes.
