Download or read book Preliminary Report on Blending Strategies for Inert matrix Fuel Recycling in LWRs written by E. A. Hoffman and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Various recycle strategies have been proposed to manage the inventory of transuranics in commercial spent nuclear fuel (CSNF), with a particular goal of increasing the loading capacity of spent fuel and reprocessing wastes in the Yucca Mountain repository. Transuranic recycling in commercial LWRs can be seen as a viable means of slowing the accumulation of transuranics in the nationwide CSNF stockpile. Furthermore, this type of approach is an important first step in demonstrating the benefits of a nuclear fuel cycle which incorporates recycling, such as envisioned for Generation-IV reactor systems under development. Recycling strategies of this sort are not proposed as an attempt to eliminate the need of a geologic nuclear waste repository, but as a means to enhance the usefulness of the repository currently under construction in the U.S., perhaps circumventing the need for a second facility. A US-DOE Secretarial recommendation on the need for the construction of a second geologic repository is required by 2010. The Advanced Fuel Cycle Initiative (AFCI) has supported a breadth of work to evaluate the ideal transuranic separation and recycle strategy. Previous AFCI studies of LWR-based transmutation have considered the benefits of homogeneously recycling plutonium, plutonium and neptunium, and all transuranic (TRU) species. A study of a wide range of hypothetical separation schemes (Pu, Pu+Np, Pu+Np+Am, etc.) with multi-recycling has also been performed, focusing on the proliferation resistance of the various fuel cycles and fuel handling issues. The direct recycle of the recovered TRU from spent inert-matrix fuel (IMF) into new IMF was found to be quite limited due to the rapid burndown of the fissile plutonium. The IMF is very effective at destroying the fissile fraction of the TRU with destruction rates in excess of 80% of the fissile material without recycling the IMF. Blending strategies have been proposed to mitigate the rapid burndown of the fissile plutonium by mixing high fissile feed from new sources (e.g., spent UO{sub 2} pins) with the low fissile material recovered from the recycled transmutation fuel. The blending of the fuels is anticipated to aid the multi-recycle of the transuranics. A systematic study of blending strategies (for both IMF and MOX) has been initiated and is currently ongoing. This work extends the previous study that considered separation strategies for plutonium, neptunium, and americium recycling in MOX, CORAIL, and IMF{sub 6} by considering blending schemes and approach to continuous recycle. Plutonium and americium are recycled in order to reduce the intermediate term (100 to 1500 years after spent fuel irradiation) decay heat of the disposed waste which accounts for the bulk of the repository heating. Since the long-term released dose from the repository is dominated by neptunium, it is sensible to consume it by transmutation in a reactor, as well. Curium accounts for {approx}0.6% of the TRU mass in spent UO{sub 2} fuel ({approx}0.008% of the heavy metal), but does constitute significantly higher fractions in spent transmutation fuels. This initial evaluation will focus on blending strategies for the multirecycling of Pu+Np+Am. The impact of curium recycle will be investigated as part of the systematic study of blending strategies. The initial study focuses on understanding a simple strategy for IMF recycle and blending. More complex strategies (i.e., heterogeneous assemblies) will be evaluated later in the year, including enriched uranium support options. Currently, a preliminary study of a serial blending strategy has been performed in order to evaluate the impact of blending on the performance of the IMF recycle and to evaluate the potential for continuous or infinite recycle. The continuous recycle of Pu+Np+Am in IMF would allow for complete destruction of all heat contributing actinides in the same LWRs that originally produced them. The only transuranics sent to the repository would be those lost in reprocessing and curium if it is not eventually recycled.
Download or read book Fuel Cycle Scenario Definition Evaluation and Trade offs written by J. D. Smith and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report aims to clarify many of the issues being discussed within the AFCI program, including Inert Matrix Fuel (IMF) versus Mixed Oxide (MOX) fuel, single-pass versus multi-pass recycling, thermal versus fast reactors, potential need for transmutation of technetium and iodine, and the value of separating cesium and strontium. It documents most of the work produced by INL, ANL, and SNL personnel under their Simulation, Evaluation, and Trade Study (SETS) work packages during FY2005 and the first half of FY2006. This report represents the first attempt to calculate a full range of metrics, covering all four AFCI program objectives - waste management, proliferation resistance, energy recovery, and systematic management/economics/safety - using a combination of "static" calculations and a system dynamic model, DYMOND. In many cases, we examine the same issue both dynamically and statically to determine the robustness of the observations. All analyses are for the U.S. reactor fleet. This is a technical report, not aimed at a policy-level audience. A wide range of options are studied to provide the technical basis for identifying the most attractive options and potential improvements. Option improvement could be vital to accomplish before the AFCI program publishes definitive cost estimates. Information from this report will be extracted and summarized in future policy-level reports. Many dynamic simulations of deploying those options are included. There are few "control knobs" for flying or piloting the fuel cycle system into the future, even though it is dark (uncertain) and controls are sluggish with slow time response: what types of reactors are built, what types of fuels are used, and the capacity of separation and fabrication plants. Piloting responsibilities are distributed among utilities, government, and regulators, compounding the challenge of making the entire system work and respond to changing circumstances. We identify four approaches that would increase our ability to pilot the fuel cycle system: (1) have a recycle strategy that could be implemented before the 2030-2050 approximate period when current reactors retire so that replacement reactors fit into the strategy, (2) establish an option such as multi-pass blended-core IMF as a downward plutonium control knob and accumulate waste management benefits early, (3) establish fast reactors with flexible conversion ratio as a future control knob that slowly becomes available if/when fast reactors are added to the fleet, and (4) expand exploration of blended assemblies and cores, which appear to have advantages and agility. Initial results suggest multi-pass full-core MOX appears to be a less effective way than multi-pass blended core IMF to manage the fuel cycle system because it requires higher TRU throughput while more slowly accruing waste management benefits. Single-pass recycle approaches for LWRs (we did not study the VHTR) do not meet AFCI program objectives and could be considered a "dead end". Fast reactors appear to be effective options but a significant number of fast reactors must be deployed before the benefit of such strategies can be observed.
Download or read book Current Comparison of Advanced Fuel Cycle Options written by R. N. Hill and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The nuclear fuel cycle includes mining, enrichment, nuclear power plants, recycling (if done), and residual waste disposition. The U.S. Advanced Fuel Cycle Initiative (AFCI) has four program objectives to guide research on how best to glue these pieces together, as follows: waste management, proliferation resistance, energy recovery, and systematic management/economics/safety. We have developed a comprehensive set of metrics to evaluate fuel cycle options against the four program objectives. The current list of metrics is long-term heat, long-term dose, radiotoxicity and weapons usable material. This paper describes the current metrics and initial results from comparisons made using these metrics. The data presented were developed using a combination of "static" calculations and a system dynamic model, DYMOND. In many cases, we examine the same issue both dynamically and statically to determine the robustness of the observations. All analyses are for the U.S. reactor fleet. This work aims to clarify many of the issues being discussed within the AFCI program, including Inert Matrix Fuel (IMF) versus Mixed Oxide (MOX) fuel, single-pass versus multi-pass recycling, thermal versus fast reactors, and the value of separating cesium and strontium. The results from a series ofdynamic simulations evaluating these options are included in this report. The model interface includes a few "control knobs" for flying or piloting the fuel cycle system into the future. The results from the simulations show that the future is dark (uncertain) and that the system is sluggish with slow timeresponse times to changes (i.e., what types of reactors are built, what types of fuels are used, and the capacity of separation and fabrication plants). Piloting responsibilities are distributed among utilities, government, and regulators, compounding the challenge of making the entire system work and respond to changing circumstances. We identify four approaches that would increase our chances of a sustainable fuel cycle system: (1) have a recycle strategy that could be implemented before the 2030-2050approximate period when current reactors retire so that replacement reactors fit into the strategy, (2) establish an option such as multi-pass blended-core IMF as a downward Pu control knob and accumulatewaste management benefits early, (3) establish fast reactors with flexible conversion ratio as a future control knob that slowly becomes available if/when fast reactors are added to the fleet, and (4) expand exploration of heterogeneous assemblies and cores, which appear to have advantages such as increased agility. Initial results suggest multi-pass full-core MOX appears to be a less effective way than multi-pass blended core IMF to manage the fuel cycle system because it requires higher TRU throughput while accruing waste management benefits at a slower rate. Single-pass recycle approaches for LWRs do not meet AFCI program objectives and could be considered a "dead end." We did not study the Very High Temperature Reactor (VHTR). Fast reactors appear to be effective options but a significant number of fast reactors must be deployed before the benefit of such strategies can be observed.
Download or read book Thorium Fuel Cycle written by International Atomic Energy Agency and published by . This book was released on 2005 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt: Provides a critical review of the thorium fuel cycle: potential benefits and challenges in the thorium fuel cycle, mainly based on the latest developments at the front end of the fuel cycle, applying thorium fuel cycle options, and at the back end of the thorium fuel cycle.
Download or read book Advances in High Temperature Gas Cooled Reactor Fuel Technology written by International Atomic Energy Agency and published by . This book was released on 2012-06 with total page 639 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.
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 The Economics of the Nuclear Fuel Cycle written by OECD Nuclear Energy Agency and published by Nuclear Energy Agency, Organisation for Economic Co-operation and Development ; Washington, D.C. : OECD Publications and Information Centre. This book was released on 1994 with total page 186 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book State of the art Report on the Progress of Nuclear Fuel Cycle Chemistry written by and published by . This book was released on 2018 with total page 148 pages. Available in PDF, EPUB and Kindle. Book excerpt: The implementation of advanced nuclear systems requires that new technologies associated with the back end of the fuel cycle are developed. The separation of minor actinides from other fuel components is one of the advanced concepts being studied to help close the nuclear fuel cycle and to improve the long-term effects on the performance of geological repositories. Separating spent fuel elements and subsequently converting them through transmutation into short-lived nuclides should considerably reduce the longterm risks associated with nuclear power generation.
Download or read book Nuclear Waste Conditioning written by France. Commissariat à l'énergie atomique (CEA) and published by Le Moniteur Editions. This book was released on 2009 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Government Reports Announcements Index written by and published by . This book was released on 1989 with total page 964 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Future of Nuclear Fuel Cycle written by and published by . This book was released on 2011 with total page 237 pages. Available in PDF, EPUB and Kindle. Book excerpt: "In this analysis we have presented a method that provides insight into future fuel cycle alternatives by clarifying the complexity of choosing an appropriate fuel cycle in the context of the distribution of burdens and benefits between generations. The current nuclear power deployment practices, together with three future fuel cycles were assessed."--Page 227.
Download or read book Status and Trends in Spent Fuel Reprocessing written by International Atomic Energy Agency and published by IAEA. This book was released on 2005 with total page 116 pages. Available in PDF, EPUB and Kindle. Book excerpt: The management of spent fuel arising from nuclear power production is a crucial issue for the sustainable development of nuclear energy. The IAEA has issued several publications in the past that provide technical information on the global status and trends in spent fuel reprocessing and associated topics, and one reason for this present publication is to provide an update of this information which has mostly focused on the conventional technology applied in the industry. However, the scope of this publication has been significantly expanded in an attempt to make it more comprehensive and by including a section on emerging technologies applicable to future innovative nuclear systems, as are being addressed in such international initiatives as INPRO, Gen IV and MICANET. In an effort to be informative, this publication attempts to provide a state-of-the-art review of these technologies, and to identify major issues associated with reprocessing as an option for spent fuel management. It does not, however, provide any detailed information on some of the related issues such as safety or safeguards, which are addressed in other relevant publications.
Download or read book Management of Recyclable Fissile and Fertile Materials written by and published by . This book was released on 2007 with total page 96 pages. Available in PDF, EPUB and Kindle. Book excerpt: Interest in nuclear energy continues to grow in many countries as a means to ensure security of energy supply and to limit greenhouse gas emissions from the power sector. In this context, recyclable materials constitute an asset for broadening the resource base for nuclear fuel supply, especially in medium- and long-term perspectives. This report provides an overview of recyclable fissile and fertile materials inventories which can be reused as nuclear fuel. It reviews the options available for managing those materials, through recycling and/or disposal. The potential energetic value of recyclable materials is assessed, taking into account the variability of retrievable energy contents of various materials according to technology and strategy choices made by the owners of the materials. The analyses contained in this report will be of particular interest to energy policy makers and to nuclear fuel cycle experts. Also available in this series: Innovation in Nuclear Energy Technology (2007) Forty Years of Uranium Resources, Production and Demand in Perspective: The Red Book Retrospective (2006) Nuclear Power Plant Life Management and Longer-term Operation (2006)
Download or read book Data Requirements and Maintenance of Records for Spent Fuel Management written by International Atomic Energy Agency and published by . This book was released on 2006 with total page 172 pages. Available in PDF, EPUB and Kindle. Book excerpt: Provides a state of the art review of spent fuel data management, including what data need to be gathered for the relevant activities in spent fuel management and how to maintain them by the responsible bodies at various stages of the nuclear fuel cycle.
Download or read book Nuclear Fuel Cycle Simulation System VISTA written by International Atomic Energy Agency and published by IAEA. This book was released on 2007 with total page 112 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Design and Operation of High Level Waste Vitrification and Storage Facilities written by International Atomic Energy Agency and published by . This book was released on 1992 with total page 114 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report gives an up to date review of high level waste vitrification and storage facilities currently in an advanced stage of implementation.
Download or read book Plutonium and Highly Enriched Uranium 1996 written by David Albright and published by . This book was released on 1997 with total page 544 pages. Available in PDF, EPUB and Kindle. Book excerpt: Plutonium and highly enriched uranium (HEU) are the basic materials used in nuclear weapons. Plutonium also plays an important part in the generation of nuclear electricity. Knowing how much plutonium and HEU exists, where and in which form is vital for international security and nuclear commerce. This book is a thorough revision of the World Inventory of Plutonium and highly Enriched Uranium, 1992. It provides a rigorous and comprehensive assessment of the amounts of plutonium and HEU in military and civilian programmes, in nuclear and non-nuclear weapon states, and in countries seeking to acquire nuclear weapons. The capibilities that exist for producing these materials around the world are examined in depth, as are the policy issues raised by them. Containing much new information, this book is indispensable to all those concerned with the great contemporary issues in international nuclear relations: arms reductions in the nuclear weapon states, nuclear proliferation, nuclear smuggling, the roles of plutonium and enriched uranium in the nuclear fuel-cycle, and the disposition of surplus weapon material.
