Download or read book U S EURATOM INERI Development of Inert Matrix Fuels for Plutonium and Minor Actinide Management in LWRs Fuel Requirements and Down Select Report written by Pavel Medvedev and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report documents the first milestone of the International Nuclear Energy Research Initiative (INERI) U.S./Canada Joint Proposal entitled "Development of Inert Matrix Fuels for Plutonium and Minor Actinide Management in Power Reactors." The milestone represents the assessment and preliminary study of a variety of fuels that hold promise as transmutation and minor actinide burning fuel compositions for light water reactors. The most promising fuels of interest to the participants on this INERI program have been selected for further study. These fuel compositions are discussed in this report.
Download or read book AECL U S INERI Development of Inert Matrix Fuels for Plutonium and Minor Actinide Management in Power Reactors Fuel Requirements and Down Select Report written by Pavel Medvedev and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report documents the first milestone of the International Nuclear Energy Research Initiative (INERI) U.S./Euratom Joint Proposal 1.8 entitled "Development of Inert Matrix Fuels for Plutonium and Minor Actinide Management in Light-Water Reactors." The milestone represents the assessment and preliminary study of a variety of fuels that hold promise as transmutation and minor actinide burning fuel compositions for light-water reactors. The most promising fuels of interest to the participants on this INERI program have been selected for further study. These fuel compositions are discussed in this report.
Download or read book Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors written by International Atomic Energy Agency and published by IAEA. This book was released on 2006 with total page 100 pages. Available in PDF, EPUB and Kindle. Book excerpt: The reactors around the world have produced more than 2000 tonnes of plutonium, contained in spent fuel or as separated forms through reprocessing. Disposition of fissile materials has become a primary concern of nuclear non-proliferation efforts worldwide. There is a significant interest in IAEA Member States to develop proliferation resistant nuclear fuel cycles for incineration of plutonium such as inert matrix fuels (IMFs). This publication reviews the status of potential IMF candidates and describes several identified candidate materials for both fast and thermal reactors: MgO, ZrO2, SiC, Zr alloy, SiAl, ZrN; some of these have undergone test irradiations and post irradiation examination. Also discussed are modelling of IMF fuel performance and safety analysis. System studies have identified strategies for both implementation of IMF fuel as homogeneous or heterogeneous phases, as assemblies or core loadings and in existing reactors in the shorter term, as well as in new reactors in the longer term.
Download or read book Fertile Free Fuels for Plutonium and Minor Actinides Burning in LWRs written by Yi Zhang and published by . This book was released on 2003 with total page 128 pages. Available in PDF, EPUB and Kindle. Book excerpt: The feasibility of using various uranium-free fuels for plutonium incineration in present light water reactors is investigated. Two major categories of inert matrix fuels are studied: composite ceramic fuel particles dispersed in another ceramic matrix (CERCER) and ceramic fuel particles dispersed into a metallic matrix (CERMET). In the category of CERCER, the current world wide research effort has been focused on three matrix candidates: (1) Spinel (MgAl2O4); (2) CeO2, and (3) MgO. In contrast, there are still no emerging commonly accepted matrix candidates for a CERMET. The fuel may consist of plutonium, minor actinides (MA), or both which are termed trans-uranium (TRU) fuel. The transmutation rate and the transmuted fraction of initial loadings are calculated using CASMO-4. Different inert matrix fuels have similar burning abilities in terms of how much and how fast the Pu, MA or TRU can be burned, and they are all superior to the mixed UO2-PuO2 (MOX) fuel. From this point of view, there is no good reason to favor one inert matrix over another. The burning rates in terms of kg/(GWe-Year) of different inert matrix fuels are quite stable with regard to changing the moderation level (or H/HM ratio) in the core. Changing initial loadings and changing power densities can not result in large change in the burned percentage of initial loadings and burning rate. Lack of U-238 and the neutronic characteristics of plutonium lead to degradation of safety related kinetic parameters. It is found that various inert matrix fuels have similar values for the Doppler coefficient, moderator temperature coefficient, void coefficient, boron worth and effective delayed neutron fraction [beta]eff. But their Doppler coefficients are much smaller than those of MOX and UO2 fuels. Both inert matrix fuels and MOX fuel have a much smaller effective delayed neutron fraction than UO2 fuel. IMF fuel's value is smaller than that of UO2 fuel, but close to that of MOX. The void coefficient is also a potential problem. The coolant void reactivity worth becomes positive if the void fraction reaches 80 percent at beginning of life for boron concentration of 1500 ppm. This is confirmed by MCNP- 4C and modified CASMO-4 calculations. The situation is generally much worse at BOL than at EOL. This is of concern during loss of coolant accidents. Two options are explored in order to improve safety coefficients: 1. Adding fertile materials into IMF fuel pins; 2. Adding fertile fuel pins into IMF fuel assemblies. UO2 and ThO2 are used as fertile additives. In option 1 it is found that adding UO2 will result in a worse degradation of burning ability. However, adding UO2 provides a better Doppler coefficient than adding ThO2. Adding about 20 w/o of UO2 achieves a BOL Doppler coefficient and other safety coefficients comparable to the traditional UO2 fuel. Yet, the fuel still has a much better burning percentage than MOX fuel for Pu (47.5% versus 13.2%) and for MA (36.1% versus 19.0%), and a much better burning rate for Pu (834 versus 285 kg/GWe-Year) and for MA (98 versus 63 kg/GWe-Year). In option 2 it is found that in order to reach the same level of safety coefficients, the burning rate of the minor actinides becomes comparable to that of MOX: 68.7 versus 63.3 kg/GWe-Year. Thus the option of adding fertile material into the fuel pins is preferable over a heterogeneous assembly option if fast burning of minor actinides is favored.
Download or read book Fuel Design for the U S Accelerator Driven Transmutation System written by and published by . This book was released on 2002 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: The U.S. concept for actinide transmutation is currently envisioned as a system to destroy plutonium as well as minor actinides in a single or two tier system. In order to maximize the actinide destruction rate, an inert matrix fuel is used. The effectiveness of transmutation in reducing the actinide inventory is linked to the development of a robust fuel system, capable of achieving very high burnup. Very little fuel performance data has been generated to date on inert matrix systems, and there are several issues specific to the behavior of higher actinides that do not allow extension of the existing uranium-plutonium fuel database to these new fuels. These issues include helium production, fuel-cladding-chemical-interaction, and americium migration. In the early 1990's, two U-Pu-Zr metal alloy fuel elements containing 1.2 wt.% Am and 1.3 wt.% Np were fabricated and irradiated to approximately 6 at.% burnup in the Experimental Breeder Reactor-II. Postirradiation examination results were not published; however the recent interest in fuel for actinide transmutation has prompted a reexamination of this data. The results of the postirradiation examination of this experiment, including gas sampling, metallography, and gamma scanning are discussed. Available data on inert matrix fuels and other fuels incorporating actinides are used to assess the implications of minor-actinide specific issues on transmuter fuel. Considerations for the design of nitride and oxide fuels, metallic fuels, and metal-matrix dispersion fuels are discussed.
Download or read book Plutonium Fuel written by OECD Nuclear Energy Agency and published by Organisation for Economic Co-operation and Development ; [Washington, D.C. : OECD Publications and Information Centre. This book was released on 1989 with total page 170 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Optimum Plutonium Inert Matrix Fuel Form for Reactor based Plutonium Disposition written by James S. Tulenko and published by . This book was released on 2005 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Barnwell Nuclear Fuels Plant Applicability Study written by and published by . This book was released on 1978 with total page 268 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Optimum Plutonium Inert Matrix Fuel Form for Reactor Based Plutonium Disposition written by J. Wang and published by . This book was released on 2004 with total page 5 pages. 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.
Download or read book The Optimum Plutonium Inert Matrix Fuel Form for Reactor Based Plutonium Disposition written by and published by . This book was released on 2004 with total page 5 pages. 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.
Download or read book Space Exploration Initiative Fuels Materials and Related Nuclear Propulsion Technologies Panel written by Fuels, Materials, and Related Technologies Panel (U.S) and published by . This book was released on 1993 with total page 326 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Solubility Tests on Inert Matrix Fuels for Plutonium Disposition in LWRs written by N. Portaro and published by . This book was released on 2000 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Development Status of Metallic Dispersion and Non Oxide Advanced and Alternative Fuels for Power and Research Reactors written by International Atomic Energy Agency and published by . This book was released on 2003 with total page 112 pages. Available in PDF, EPUB and Kindle. Book excerpt: Summarises knowledge accumulated in fuel research since the beginning of the 1960s. This publication concentrates on the "advanced fuels" for the current different types of reactors, including metallic, carbide and nitride fuels for fast reactors, so-called ""cold"" fuels and fuels to burn excess ex-weapons plutonium in thermal power reactors.
Download or read book Utilization of Minor Actinides as a Fuel Component for Ultra Long Life Bhr Configurations written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This project assessed the advantages and limitations of using minor actinides as a fuel component to achieve ultra-long life Very High Temperature Reactor (VHTR) configurations. Researchers considered and compared the capabilities of pebble-bed and prismatic core designs with advanced actinide fuels to achieve ultra-long operation without refueling. Since both core designs permit flexibility in component configuration, fuel utilization, and fuel management, it is possible to improve fissile properties of minor actinides by neutron spectrum shifting through configuration adjustments. The project studied advanced actinide fuels, which could reduce the long-term radio-toxicity and heat load of high-level waste sent to a geologic repository and enable recovery of the energy contained in spent fuel. The ultra-long core life autonomous approach may reduce the technical need for additional repositories and is capable to improve marketability of the Generation IV VHTR by allowing worldwide deployment, including remote regions and regions with limited industrial resources. Utilization of minor actinides in nuclear reactors facilitates developments of new fuel cycles towards sustainable nuclear energy scenarios.
Download or read book Development of Advanced Mixed Oxide Fuels for Plutonium Management written by and published by . This book was released on 1997 with total page 7 pages. Available in PDF, EPUB and Kindle. Book excerpt: A number of advanced Mixed Oxide (MOX) fuel forms are currently being investigated at Los Alamos National Laboratory that have the potential to be effective plutonium management tools. Evolutionary Mixed Oxide (EMOX) fuel is a slight perturbation on standard MOX fuel, but achieves greater plutonium destruction rates by employing a fractional nonfertile component. A pure nonfertile fuel is also being studied. Initial calculations show that the fuel can be utilized in existing light water reactors and tailored to address different plutonium management goals (i.e., stabilization or reduction of plutonium inventories residing in spent nuclear fuel). In parallel, experiments are being performed to determine the feasibility of fabrication of such fuels. Initial EMOX pellets have successfully been fabricated using weapons-grade plutonium.
Download or read book RERTR Fuel Developmemt and Qualification Plan written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: In late 2003 it became evident that U-Mo aluminum fuels under development exhibited significant fuel performance problems under the irradiation conditions required for conversion of most high-powered research reactors. Solutions to the fuel performance issue have been proposed and show promise in early testing. Based on these results, a Reduced Enrichment Research and Test Reactor (RERTR) program strategy has been mapped to allow generic fuel qualification to occur prior to the end of FY10 and reactor conversion to occur prior to the end of FY14. This strategy utilizes a diversity of technologies, test conditions, and test types. Scoping studies using miniature fuel plates will be completed in the time frame of 2006-2008. Irradiation of larger specimens will occur in the Advanced Test Reactor (ATR) in the United States, the Belgian Reactor-2 (BR2) reactor in Belgium, and in the OSIRIS reactor in France in 2006-2009. These scoping irradiation tests provide a large amount of data on the performance of advanced fuel types under irradiation and allow the down selection of technology for larger scale testing during the final stages of fuel qualification. In conjunction with irradiation testing, fabrication processes must be developed and made available to commercial fabricators. The commercial fabrication infrastructure must also be upgraded to ensure a reliable low enriched uranium (LEU) fuel supply. Final qualification of fuels will occur in two phases. Phase I will obtain generic approval for use of dispersion fuels with density less than 8.5 g-U/cm3. In order to obtain this approval, a larger scale demonstration of fuel performance and fabrication technology will be necessary. Several Materials Test Reactor (MTR) plate-type fuel assemblies will be irradiated in both the High Flux Reactor (HFR) and the ATR (other options include the BR2 and Russian Research Reactor, Dmitrovgrad, Russia [MIR] reactors) in 2008-2009. Following postirradiation examination, a report detailing very-high density fuel behavior will be submitted to the U.S. Nuclear Regulatory Commission (NRC). Assuming acceptable fuel behavior, it is anticipated that NRC will issue a Safety Evaluation Report granting generic approval of the developed fuels based on the qualification report. It is anticipated that Phase I of fuel qualification will be completed prior to the end of FY10. Phase II of the fuel qualification requires development of fuels with density greater than 8.5 g-U/cm3. This fuel is required to convert the remaining few reactors that have been identified for conversion. The second phase of the fuel qualification effort includes both dispersion fuels with fuel particle volume loading on the order of 65 percent, and monolithic fuels. Phase II presents a larger set of technical unknowns and schedule uncertainties than phase I. The final step in the fuel qualification process involves insertion of lead test elements into the converting reactors. Each reactor that plans to convert using the developed high-density fuels will develop a reactor specific conversion plan based upon the reactor safety basis and operating requirements. For some reactors (FRM-II, High-Flux Isotope Reactor [HFIR], and RHF) conversion will be a one-step process. In addition to the U.S. fuel development effort, a Russian fuel development strategy has been developed. Contracts with Russian Federation institutes in support of fuel development for Russian are in place.
Download or read book Cittadini extracomunitari in Italia written by and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
