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Author : James Kevin Presley
Publisher :
ISBN 13 :
Total Pages : 58 pages
Book Rating : 4.:/5 (181 download)
Download or read book Fuel Trajectory Analysis of Advanced Nuclear Energy Fuel Cycles and Systems written by James Kevin Presley and published by . This book was released on 1980 with total page 58 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
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ISBN 13 : 9780982800843
Total Pages : 237 pages
Book Rating : 4.8/5 (8 download)
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.
Author : Lawrence Fernando Bronk
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (664 download)
Download or read book Comparative Analysis of Advanced Nuclear Fuel Cycles Over Limited Time Horizons written by Lawrence Fernando Bronk and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear power currently produces approximately 20% of all U.S. commercial electric energy and is the leading source of carbon-free energy production. It is well known that the current uranium-oxide (UOX) fuel cycle produces large quantities of transuranic (TRU) materials in the form of "nuclear waste". Reducing the quantity of the long lived radioisotopes contained within the spent fuel as well as increasing resource utilization will be fundamental necessities for ensuring the viability of nuclear power. Inert matrix fuels (IMF) could potentially allow current generation light-water reactors to achieve a significant reduction in the amount of transuranic waste that is currently being generated as a byproduct of the UOX cycle. To characterize the relative performance of an IMF system to other TRU reduction systems currently under consideration by the Department of Energy, such as a fast burner reactor (FBR), we performed a fuel cycle simulation. Using ORIGEN 2.2 and an in-house developed collision probability code, VBUDS, we compared each cycle's actinide burning abilities over a 100 year time period by generating an endpoint discharge isotopic vector for each. We also performed a sensitivity study of an IMF system to the beginning of life fuel composition. We have found that a one pass IMF system with a burn up of 750 MWd/kg will perform comparably to a FBR in recycle system with a burn up of 140 MWd/kg, where the FBR system slightly outperforms the IMF system. An IMF system using a burn of 850 MWd/kg will almost always outperform the FBR cycle, especially if there is an active cooling period after the nuclear waste is emplaced. The IMF sensitivity study found that the decay heat of the IMF systems, 750 MWd/kg and 850 MWd/kg, was largely unaffected by the burn up or cooling period of the UOX spent fuel used to make the IMF.
Author : Lara Marie Pierpoint
Publisher :
ISBN 13 :
Total Pages : 126 pages
Book Rating : 4.:/5 (255 download)
Download or read book Analyzing the Proliferation Resistance of Advanced Nuclear Fuel Cycles written by Lara Marie Pierpoint and published by . This book was released on 2008 with total page 126 pages. Available in PDF, EPUB and Kindle. Book excerpt: A methodology to assess proliferation resistance of advanced nuclear energy systems is investigated. The framework, based on Multi-Attribute Utility Theory (MAUT), is envisioned for use within early-stage fuel cycle simulations. Method assumptions and structure are explained, and reference technology cases are presented to test the model. Eleven metrics are presented to evaluate the proliferation resistance of once-through, COmbined Non-Fertile and Uranium (CONFU), Mixed-Oxide (MOX), and Advanced Burner Reactor (ABR) fuel cycles. The metrics are roughly categorized in three groups: material characteristics, material handling characteristics, and "inherent" facility characteristics. Each metric is associated with its own utility function, and is weighted according to the proliferation threat of interest. Results suggest that transportation steps are less proliferation-resistant than stationary facilities, and that the ABR fuel cycle employing reactors with low conversion ratios are particularly safe. Nearly all steps of the fuel cycles analyzed are more proliferation resistant to a terrorist threat than to a host nation threat (which has more resources to devote toward proliferation activities). The open light water reactor (LWR) and MOX cycles appear to be the most vulnerable of all cycles analyzed. CONFU proliferation resistance is similar to that of the ABR with conversion ratios 0.5 and 1.0; these are all approximately in between the values ascribed to LWR/MOX (at the low end) and ABR with conversion ratio zero (with the highest proliferation resistance). Preliminary studies were conducted to determine the sensitivity of the results to weighting function structure and values. Several different weighting functions were applied to the utility values calculated for the once-through and CONFU fuel cycles. The tests showed very little change in the ultimate trends and conclusions drawn from each fuel cycle calculation. These conclusions, however, are far from definitive. Limitations of the model are discussed and demonstrated. Recommendations for improving the model are made, including a call for in-depth evaluation of weighting function structures and values, and an examination of quantitative links between assumptions and utilities. Ultimate conclusions include that the numerical values produced by the analysis are not fully and accurately instructive, and analysts should recognize that the greatest gifts of the assessment may come from performing the investigation.
Download or read book Using Systems Analysis to Guide Fuel Cycle Development written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Systems Analysis is an important tool for guiding the development of an advanced fuel cycle. The process of nuclear research, development, and demonstration takes a relatively long time, and can require a significant amount of expensive testing. It is beneficial to minimize the amount of testing required, and systems analysis should be used as one of the first steps in downselecting technologies and streamlining the requirements. This paper discusses the application of systems analysis to advanced fuel cycle development, including using it is a tool for initial investigation of sets of technology options, as well for planning timelines for testing and downselection amongst sets of technology options. The use of Technology Readiness Levels (TRLs) in fuel cycle development is explained, together with the connection between TRLs and systems analysis via requirements development. TRLs applied to transmutation fuel development is used as an example; transmutation fuel development, including testing and qualification, is generally considered to be the most time-intensive process, from a technical point of view, in fuel cycle development, and can be the deciding factor in determining the shortest time possible for implementing an advanced fuel cycle. Using systems analysis to inform technology readiness levels provides a disciplined and informed process for advanced fuel cycle development.
Author :
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ISBN 13 :
Total Pages : 76 pages
Book Rating : 4.:/5 (925 download)
Download or read book Nuclear Fuel Cycle System Simulation Tool Based on High-fidelity Component Modeling written by and published by . This book was released on 2014 with total page 76 pages. Available in PDF, EPUB and Kindle. Book excerpt: The DOE is currently directing extensive research into developing fuel cycle technologies that will enable the safe, secure, economic, and sustainable expansion of nuclear energy. The task is formidable considering the numerous fuel cycle options, the large dynamic systems that each represent, and the necessity to accurately predict their behavior. The path to successfully develop and implement an advanced fuel cycle is highly dependent on the modeling capabilities and simulation tools available for performing useful relevant analysis to assist stakeholders in decision making. Therefore a high-fidelity fuel cycle simulation tool that performs system analysis, including uncertainty quantification and optimization was developed. The resulting simulator also includes the capability to calculate environmental impact measures for individual components and the system. An integrated system method and analysis approach that provides consistent and comprehensive evaluations of advanced fuel cycles was developed. A general approach was utilized allowing for the system to be modified in order to provide analysis for other systems with similar attributes. By utilizing this approach, the framework for simulating many different fuel cycle options is provided. Two example fuel cycle configurations were developed to take advantage of used fuel recycling and transmutation capabilities in waste management scenarios leading to minimized waste inventories.
Download or read book Uncertainty Analyses of Advanced Fuel Cycles written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Department of Energy is developing technology, experimental protocols, computational methods, systems analysis software, and many other capabilities in order to advance the nuclear power infrastructure through the Advanced Fuel Cycle Initiative (AFDI). Our project, is intended to facilitate will-informed decision making for the selection of fuel cycle options and facilities for development.
Download or read book VISION -- A Dynamic Model of the Nuclear Fuel Cycle written by and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Fuel Cycle Initiative's (AFCI) fundamental objective is to provide technology options that - if implemented - would enable long-term growth of nuclear power while improving sustainability and energy security. The AFCI organization structure consists of four areas; Systems Analysis, Fuels, Separations and Transmutations. The Systems Analysis Working Group is tasked with bridging the program technical areas and providing the models, tools, and analyses required to assess the feasibility of design and deploy?ment options and inform key decision makers. An integral part of the Systems Analysis tool set is the development of a system level model that can be used to examine the implications of the different mixes of reactors, implications of fuel reprocessing, impact of deployment technologies, as well as potential?exit? or?off ramp? approaches to phase out technologies, waste management issues and long-term repository needs. The Verifiable Fuel Cycle Simulation Model (VISION) is a computer-based simulation model that allows performing dynamic simulations of fuel cycles to quantify infrastructure requirements and identify key trade-offs between alternatives. VISION is intended to serve as a broad systems analysis and study tool applicable to work conducted as part of the AFCI (including costs estimates) and Generation IV reactor development studies.
Download or read book Fuel Cycle Analysis of Once-through Nuclear Systems written by and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Once-through fuel cycle systems are commercially used for the generation of nuclear power, with little exception. The bulk of these once-through systems have been water-cooled reactors (light-water and heavy water reactors, LWRs and HWRs). Some gas-cooled reactors are used in the United Kingdom. The commercial power systems that are exceptions use limited recycle (currently one recycle) of transuranic elements, primarily plutonium, as done in Europe and nearing deployment in Japan. For most of these once-through fuel cycles, the ultimate storage of the used (spent) nuclear fuel (UNF, SNF) will be in a geologic repository. Besides the commercial nuclear plants, new once-through concepts are being proposed for various objectives under international advanced nuclear fuel cycle studies and by industrial and venture capital groups. Some of the objectives for these systems include: (1) Long life core for remote use or foreign export and to support proliferation risk reduction goals - In these systems the intent is to achieve very long core-life with no refueling and limited or no access to the fuel. Most of these systems are fast spectrum systems and have been designed with the intent to improve plant economics, minimize nuclear waste, enhance system safety, and reduce proliferation risk. Some of these designs are being developed under Generation IV International Forum activities and have generally not used fuel blankets and have limited the fissile content of the fuel to less than 20% for the purpose on meeting international nonproliferation objectives. In general, the systems attempt to use transuranic elements (TRU) produced in current commercial nuclear power plants as this is seen as a way to minimize the amount of the problematic radio-nuclides that have to be stored in a repository. In this case, however, the reprocessing of the commercial LWR UNF to produce the initial fuel will be necessary. For this reason, some of the systems plan to use low enriched uranium (LEU) fuels. Examples of systems in this class include the small modular reactors being considered internationally; e.g. 4S [Tsuboi 2009], Hyperion Power Module [Deal 2010], ARC-100 [Wade 2010], and SSTAR [Smith 2008]. (2) Systems for Resource Utilization - In recent years, interest has developed in the use of advanced nuclear designs for the effective utilization of fuel resources. Systems under this class have generally utilized the breed and burn concept in which fissile material is bred and used in situ in the reactor core. Due to the favorable breeding that is possible with fast neutrons, these systems have tended to be fast spectrum systems. In the once-through concepts (as opposed to the traditional multirecycle approach typically considered for fast reactors), an ignition (or starter) zone contains driver fuel which is fissile material. This zone is designed to last a long time period to allow the breeding of sufficient fissile material in the adjoining blanket zone. The blanket zone is initially made of fertile depleted uranium fuel. This zone could also be made of fertile thorium fuel or recovered uranium from fuel reprocessing or natural uranium. However, given the bulk of depleted uranium and the potentially large inventory of recovered uranium, it is unlikely that the use of thorium is required in the near term in the U.S. Following the breeding of plutonium or fissile U-233 in the blanket, this zone or assembly then carries a larger fraction of the power generation in the reactor. These systems tend to also have a long cycle length (or core life) and they could be with or without fuel shuffling. When fuel is shuffled, the incoming fuel is generally depleted uranium (or thorium) fuel. In any case, fuel is burned once and then discharged. Examples of systems in this class include the CANDLE concept [Sekimoto 2001], the traveling wave reactor (TWR) concept of TerraPower [Ellis 2010], the ultra-long life fast reactor (ULFR) by ANL [Kim 2010], and the BNL fast mixed spectrum reactor (FMSR) concept [Fisher 1979]. (3) Thermal systems for resource extension - These systems were primarily considered during the INFCE/NASAP evaluations [NASAP 1979] and include various LWR designs for increasing resource utilization (both uranium and thorium). This class would include the Radkowsky seed-blanket concept. Also included in this class are the thermal reactor systems being considered for deployment as small modular reactors, such as IRIS [Carelli 2004], mPower [mPower], and NuScale [NuScale] that are all water cooled reactors. The purpose of this work is to provide relevant systems and fuel cycle information for some of these once-through fuel cycle systems. In this report, the intent is on providing information on most of the systems from open sources and from scoping studies recently done within the program. As there is insufficient fuel cycle information on the first class of systems, they are not discussed in this report.
Author : Jacob J. Jacobson
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (316 download)
Download or read book Modeling the Nuclear Fuel Cycle written by Jacob J. Jacobson and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Fuel Cycle Initiative is developing a system dynamics model as part of their broad systems analysis of future nuclear energy in the United States. The model will be used to analyze and compare various proposed technology deployment scenarios. The model will also give a better understanding of the linkages between the various components of the nuclear fuel cycle that includes uranium resources, reactor number and mix, nuclear fuel type and waste management. Each of these components is tightly connected to the nuclear fuel cycle but usually analyzed in isolation of the other parts. This model will attempt to bridge these components into a single model for analysis. This work is part of a multi-national laboratory effort between Argonne National Laboratory, Idaho National Laboratory and United States Department of Energy. This paper summarizes the basics of the system dynamics model and looks at some results from the model.
Author : Kristina D. Yancey
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (662 download)
Download or read book Environmental Aspects of Advanced Nuclear Fuel Cycles written by Kristina D. Yancey and published by . This book was released on 2010 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear power has the potential to help reduce rising carbon emissions, but to be considered sustainable, it must also demonstrate the availability of an indefinite fuel supply as well as not produce any significant negative environmental effects. The objective of this research was to evaluate the sustainability of nuclear power and to explore the nuclear fuel cycles that best meet this goal. First, the study quantified current and promising nuclear fuel cycles to be further evaluated and developed a set of objective metrics to describe the environmental effects of each cycle. The metrics included such factors as the amount of waste generated and the isotopic composition of the waste. Next, the evaluation used the International Atomic Energy Agency's Nuclear Fuel Cycle Simulation System to compute nuclide compositions at various stages of the fuel cycles. Finally, the study looked at the radioactivity of the waste generated and used this and other characteristics to determine which fuel cycle meets the objectives of sustainability. Results confirm that incorporating recycling into the fuel cycle would help reduce the volume of waste needing to be stored long-term. Also, calculations made with data from the Nuclear Fuel Cycle Simulation System predicted that the waste from fuel cycles using recycling would be slightly more radiotoxic than the open fuel cycle's waste. However, the small increase in radiotoxicity is a manageable issue and would not detract from the benefits of recycling. Therefore, recycling and reprocessing spent fuel must be incorporated into the nuclear fuel cycle to achieve sustainability.
Download or read book Development and Utilization of Mathematical Optimization in Advanced Fuel Cycle Systems Analysis written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Over the past sixty years, a wide variety of nuclear power technologies have been theorized, investigated and tested to various degrees. These technologies, if properly applied, could provide a stable, long-term, economical source of CO2-free electric power. However, the recycling of nuclear fuel introduces a degree of coupling between reactor systems which must be accounted for when making long term strategic plans. This work investigates the use of a simulated annealing optimization algorithm coupled together with the VISION fuel cycle simulation model in order to identify attractive strategies from economic, evironmental, non-proliferation and waste-disposal perspectives, which each have associated an objective function. The simulated annealing optimization algorithm works by perturbing the fraction of new reactor capacity allocated to each available reactor type (using a set of heuristic rules) then evaluating the resulting deployment scenario outcomes using the VISION model and the chosen objective functions. These new scenarios, which are either accepted or rejected according the the Metropolis Criterion, are then used as the basis for further perturbations. By repeating this process several thousand times, a family of near-optimal solutions are obtained. Preliminary results from this work using a two-step, Once-through LWR to Full-recycle/FRburner deployment scenario with exponentially increasing electric demand indicate that the algorithm is capable of nding reactor deployment pro les that reduce the long-term-heat waste disposal burden relative to an initial reference scenario. Further work is under way to re ne the current results and to extend them to include the other objective functions and to examine the optimization trade-o s that exist between these di erent objectives.
Author : Robert G. Cochran
Publisher :
ISBN 13 :
Total Pages : 406 pages
Book Rating : 4.3/5 (91 download)
Download or read book The Nuclear Fuel Cycle written by Robert G. Cochran and published by . This book was released on 1990 with total page 406 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Weifeng Zhou
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (123 download)
Download or read book Resilience Analysis of Nuclear Fuel Cycle Scenarios written by Weifeng Zhou and published by . This book was released on 2020 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear fuel cycle systems, composed of reactors, various fuels, and different cycle facilities, are complex and in constant evolution. Thanks to their abilities to make projections of industrial strategies and to assess the associated impacts on nuclear fuel cycle systems, nuclear fuel cycle scenarios are considered as a powerful tool for decision-making analyses. Scenario studies assist decision-makers in identifying the strengths and weaknesses of different strategies for a nuclear fleet evolution and then proposing possible evolution trajectories for the nuclear industry according to constraints from physics, economics, industry, etc.However, scenario studies are usually subject to different kinds of uncertainties, especially the so-called “deep uncertainty.” This concept refers to “unknown unknowns,” which scenario study results are unsuited to address. Indeed, under the impact of deep uncertainty, i.e., disruptions, the trajectories proposed by the scenario studies can become invalid: they do not satisfy the scenario constraints anymore.In order to make the trajectories valid again after disruption due to uncertainty, the first possibility is to study the resistance strategy. The resistance strategy consists of finding scenario trajectories that remain valid under the impact of uncertainty without exogenous readjustments of trajectories. However, the resistance capabilities of scenarios are limited: resistance is only adapted to uncertainties with small impact, while the impact of deep uncertainty is usually strong.As a complementary solution to the resistance strategy, we propose using resilience strategies. The resilience strategies consist of using predesigned measures, called “levers,” to readjust the scenario trajectory when the resistance strategy is insufficient. We aim to use the effect of the exogenous readjustments of trajectories, which are introduced through the levers, to counterbalance the impact of disruption and remain the trajectory valid. To evaluate the resilience of scenarios, we developed a resilience analysis framework, based on the start-of-the-art SUR (Stepwise Uncertainty Reduction) algorithm.We applied the developed resilience strategy to two scenario problems in which a simplified French nuclear fleet with uncertain power reduction is considered. To define the validity of trajectory, we imposed five constraints about the reprocessing plant utilization ratio, plutonium separation, plutonium content in MOX fuel, and spent fuel storage. In each problem, we gave a prior trajectory supposed as a result of a scenario study with a hypothesis to keep the installed power constant in the future. We assumed that following the disruption of the study context, the total electricity power is disrupted and reduced in the future. The results showed that the prior trajectories in both problems are resilient for the assumed disruptions: it is possible to keep the prior trajectories valid by readjusting the reprocessing and the MOX fuel loadings in reactors. Such results demonstrate the evolutions of the nuclear fleet in the prior trajectories are flexible in front of the disruption of total electricity power.
Author : Tyler Martin Schweitzer
Publisher :
ISBN 13 :
Total Pages : 188 pages
Book Rating : 4.:/5 (228 download)
Download or read book Improved Building Methodology and Analysis of Delay Scenarios of Advanced Nuclear Fuel Cycles with the Verifiable Fuel Cycle Simulation Model (VISION) written by Tyler Martin Schweitzer and published by . This book was released on 2008 with total page 188 pages. Available in PDF, EPUB and Kindle. Book excerpt: Keywords: Advanced Nuclear Fuel Cycles.
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ISBN 13 :
Total Pages : 85 pages
Book Rating : 4.:/5 (696 download)
Download or read book Methodology for Uncertainty Analysis of Advanced Fuel Cycles and Preliminary Results written by and published by . This book was released on 2006 with total page 85 pages. Available in PDF, EPUB and Kindle. Book excerpt: This report assesses the sensitivity and uncertainty associated with certain advanced nuclear fuel cycles due to the variance of chosen parameters and how these results relate to the deep geological nuclear waste repository. High burn up uranium oxide, mixed oxide, and fast spectrum nuclear fuels are the advanced fuel cycles considered. The parameters that are varied in these cases are: the time of advanced fuel implementation, energy growth rate, fuel burn up, and reprocessing introduction and capacity. The results analyzed are the amount of spent fuel and the amount of Pu in spent fuel in the year 2099. The advanced fuel cycle scenarios are modeled using the DANESS code developed by Argonne National Laboratory. All the fuel cycles modeled in this report are highly sensitive to the above-mentioned varied parameters. In a 0% energy growth rate case the plutonium fast burner reactor significantly reduces the amount of waste destined to the repository. Compared to current once-through fuel cycle practices, the fast reactor reduces waste by 50-52 percent. As energy demand grows, the high burn up case of 100 (GWd per ton heavy metal) fuel, as modeled in this thesis, reduces the mass destined for the repository greatest. In the 1.5% energy growth rate, spent fuel mass is reduced 32-44 percent, and in the 3.0% energy growth rate those numbers are 43-49 percent.
Download or read book Lessons Learned From Dynamic Simulations of Advanced Fuel Cycles written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Years of performing dynamic simulations of advanced nuclear fuel cycle options provide insights into how they could work and how one might transition from the current once-through fuel cycle. This paper summarizes those insights from the context of the 2005 objectives and goals of the Advanced Fuel Cycle Initiative (AFCI). Our intent is not to compare options, assess options versus those objectives and goals, nor recommend changes to those objectives and goals. Rather, we organize what we have learned from dynamic simulations in the context of the AFCI objectives for waste management, proliferation resistance, uranium utilization, and economics. Thus, we do not merely describe "lessons learned" from dynamic simulations but attempt to answer the "so what" question by using this context. The analyses have been performed using the Verifiable Fuel Cycle Simulation of Nuclear Fuel Cycle Dynamics (VISION). We observe that the 2005 objectives and goals do not address many of the inherently dynamic discriminators among advanced fuel cycle options and transitions thereof.
