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Uncertainty Analyses Of Advanced Fuel Cycles
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Book Synopsis Uncertainty Analyses of Advanced Fuel Cycles by :
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.
Book Synopsis Methodology for Uncertainty Analysis of Advanced Fuel Cycles and Preliminary Results by :
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.
Book Synopsis Uncertainty Analysis of the Utilization and Implementation of Advanced Fuel Cycles to Control Plutonium Inventories by :
Download or read book Uncertainty Analysis of the Utilization and Implementation of Advanced Fuel Cycles to Control Plutonium Inventories written by and published by . This book was released on 2007 with total page 110 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper assesses the uncertainty associated with the utilization and implementation of advanced fuel cycles to control plutonium inventories. The specific fuel cycles investigated are a partially closed cycle utilizing MOX reactors and completely closed one-tier fuel cycles utilizing fast reactors. Multiple methods for assessing these uncertainties were utilized. A scenario approach that varied the time and number of the implementation of the advanced reactors was used. It was found that the implementation of 3 FR/yr with a CR of 0.5 could reduce the amount of Pu by over 36% in reference to building 3 LWR/yr. In addition to reducing the inventory with respect to the reference LWR case, the growth rate can be reduced from an initial 22 tons Pu/ year growth to 5 tons Pu / year growth with the 2030 actual initial Pu inventory implementation cases. The MOX cases keep the Pu/ TWhe inventory slightly above 1 ton Pu/TWhe and the extremely low CR FR cases even lower than that value. Thus from this work the extremely low CR FR scenarios show the greatest ability to control the growing Pu inventory. In addition to the scenario approach a Monte Carlo uncertainty model was developed and analyzed. The uncertainty analysis showed the high burn up cases are comparable with the of [sic] the low CR FR cases in there [sic] ability to control the Pu inventory with the Pu inventories ranging from 2500 tons of Pu to 7500 tons of Pu. However, for the high burn up cases the majority of the Pu is Out-Of-Pile as opposed to the FR cases where a considerable amount of the Pu is In-Pile. From a proliferation stand point, the low CR FR case is better at the [sic] controlling the Pu inventory because the total inventories are relatively the same for the majority of the runs, and the FR cases keep most of the Pu In-Pile rather than the high burn up cases which keep most of it Out-Of-Pile. Lastly, a brief economic uncertainty model was developed. The economic results show that the once-through cycle is the cheapest with over 50% of the test cases coming in cheaper than all of the FR and MOX cases. The FR cases come out to be the next cheapest with the MOX cases being the most expensive.
Book Synopsis Management Tool for Assessment of Alternative Fuel Cycles by : Jeffrey Robert Preston
Download or read book Management Tool for Assessment of Alternative Fuel Cycles written by Jeffrey Robert Preston and published by . This book was released on 2010 with total page 100 pages. Available in PDF, EPUB and Kindle. Book excerpt: A new approach to fuel cycle uncertainty analysis and optimization is presented that combines reactor physics information, spent fuel management, and economic forecasting, which may be used to investigate effects of decisions in the design of advanced nuclear fuel cycles. The Matlab-based simulation includes isotopic mass and integral decay heat data produced by reactor physics codes in the SCALE package (SAS2, ORIGEN-ARP, and ORIGEN-S). Reactor physics data for Light Water Reactor (LWR), and metal- and oxide-fueled Liquid Metal-cooled Fast Burner Reactor (LMFBR) designs are stored in databases that the code uses as needed. Detailed models of the once through and hybrid LWR-LMFBR fuel cycles have been developed for repository decay heat analysis, determination of levelized unit electric cost (LUEC), and reprocessing of spent fuel into fast reactor fuel or targets as a means of isotopic inventory minimization. The models may be run for single estimates based on best estimates of model parameters as either a Monte Carlo uncertainty analysis or as an optimization using Genetic Algorithms (GA). Results from the LUEC calculations show the once through cycle has a bus bar cost of about $19.0mills/kWh (excluding repository and interim storage costs), and the hybrid cycle has a bus bar cost of about $26.5mills/kWh. Implementation of the hybrid cycle compared to the closed once through cycle yields an effective repository mass capacity increase by a percentage of about 30% to 60% through full reprocessing of LWR spent fuel compared to original mass definitions of the Yucca Mountain repository. The GA optimization routine allows the user to define any one of the variables present in the output structure as the fitness parameter; thus, optimization of any calculated value is possible, including economic cost, isotopic inventory, or required repository capacity. Optimization of the once through cycle with respect to LUEC gives a result of $19.2 mills/kWh when burn up approaches the upper limit of 60 GWd/t and delay time spent fuel cools after discharge approaches 200 years (including repository and interim storage costs).
Book Synopsis A VISION of Advanced Nuclear System Cost Uncertainty by :
Download or read book A VISION of Advanced Nuclear System Cost Uncertainty written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: VISION (VerifIable fuel cycle SImulatiON) is the Advanced Fuel Cycle Initiative's and Global Nuclear Energy Partnership Program's nuclear fuel cycle systems code designed to simulate the US commercial reactor fleet. The code is a dynamic stock and flow model that tracks the mass of materials at the isotopic level through the entire nuclear fuel cycle. As VISION is run, it calculates the decay of 70 isotopes including uranium, plutonium, minor actinides, and fission products. VISION. ECON is a sub-model of VISION that was developed to estimate fuel cycle and reactor costs. The sub-model uses the mass flows generated by VISION for each of the fuel cycle functions (referred to as modules) and calculates the annual cost based on cost distributions provided by the Advanced Fuel Cycle Cost Basis Report1. Costs are aggregated for each fuel cycle module, and the modules are aggregated into front end, back end, recycling, reactor, and total fuel cycle costs. The software also has the capability to perform system sensitivity analysis. This capability may be used to analyze the impacts on costs due to system uncertainty effects. This paper will provide a preliminary evaluation of the cost uncertainty affects attributable to 1) key reactor and fuel cycle system parameters and 2) scheduling variations. The evaluation will focus on the uncertainty on the total cost of electricity and fuel cycle costs. First, a single light water reactor (LWR) using mixed oxide fuel is examined to ascertain the effects of simple parameter changes. Three system parameters; burnup, capacity factor and reactor power are varied from nominal cost values and the affect on the total cost of electricity is measured. These simple parameter changes are measured in more complex scenarios 2-tier systems including LWRs with mixed fuel and fast recycling reactors using transuranic fuel. Other system parameters are evaluated and results will be presented in the paper. Secondly, the uncertainty due to variation in scheduling effects is evaluated. For example, economic impacts due to increased nuclear energy growth rates and speed-ups in deployment of fuel cycle facilities and fast reactors. Preliminary results show that significant variations in the costs of the scenarios can result from variations in burnup, capacity factor and reactor power. The paper will include new results from analysis of additional system variables and due to scheduling dynamics. Reference 1. Shropshire, D.E. et al, 2007, Advanced Fuel Cycle Cost Basis, INL/EXT-07-12107, April 2007.
Book Synopsis Advanced Nuclear Fuel Cycle Transitions by :
Download or read book Advanced Nuclear Fuel Cycle Transitions written by and published by . This book was released on 2016 with total page 248 pages. Available in PDF, EPUB and Kindle. Book excerpt: Many nuclear fuel cycle simulators have evolved over time to help understan the nuclear industry/ecosystem at a macroscopic level. Cyclus is one of th first fuel cycle simulators to accommodate larger-scale analysis with it liberal open-source licensing and first-class Linux support. Cyclus also ha features that uniquely enable investigating the effects of modeling choices o fuel cycle simulators and scenarios. This work is divided into thre experiments focusing on optimization, effects of modeling choices, and fue cycle uncertainty Effective optimization techniques are developed for automatically determinin desirable facility deployment schedules with Cyclus. A novel method fo mapping optimization variables to deployment schedules is developed. Thi allows relationships between reactor types and scenario constraints to b represented implicitly in the variable definitions enabling the usage o optimizers lacking constraint support. It also prevents wasting computationa resources evaluating infeasible deployment schedules. Deployed power capacit over time and deployment of non-reactor facilities are also included a optimization variables There are many fuel cycle simulators built with different combinations o modeling choices. Comparing results between them is often difficult. Cyclus flexibility allows comparing effects of many such modeling choices. Reacto refueling cycle synchronization and inter-facility competition among othe effects are compared in four cases each using combinations of fleet o individually modeled reactors with 1-month or 3-month time steps. There ar noticeable differences in results for the different cases. The larges differences occur during periods of constrained reactor fuel availability This and similar work can help improve the quality of fuel cycle analysi generally There is significant uncertainty associated deploying new nuclear technologie such as time-frames for technology availability and the cost of buildin advanced reactors. Historically, fuel cycle analysis has focused on answerin questions of fuel cycle feasibility and optimality. However, there has no been much work done to address uncertainty in fuel cycle analysis helpin answer questions of fuel cycle robustness. This work develops an demonstrates a methodology for evaluating deployment strategies whil accounting for uncertainty. Techniques are developed for measuring th hedging properties of deployment strategies under uncertainty. Additionally methods for using optimization to automatically find good hedging strategie are demonstrated
Book Synopsis Nuclear Fuel Cycle System Simulation Tool Based on High-fidelity Component Modeling by :
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.
Book Synopsis Advanced Fuel Cycle Economic Analysis of Symbiotic Light-Water Reactor and Fast Burner Reactor Systems by :
Download or read book Advanced Fuel Cycle Economic Analysis of Symbiotic Light-Water Reactor and Fast Burner Reactor Systems written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Advanced Fuel Cycle Economic Analysis of Symbiotic Light-Water Reactor and Fast Burner Reactor Systems, prepared to support the U.S. Advanced Fuel Cycle Initiative (AFCI) systems analysis, provides a technology-oriented baseline system cost comparison between the open fuel cycle and closed fuel cycle systems. The intent is to understand their overall cost trends, cost sensitivities, and trade-offs. This analysis also improves the AFCI Program's understanding of the cost drivers that will determine nuclear power's cost competitiveness vis-a-vis other baseload generation systems. The common reactor-related costs consist of capital, operating, and decontamination and decommissioning costs. Fuel cycle costs include front-end (pre-irradiation) and back-end (post-iradiation) costs, as well as costs specifically associated with fuel recycling. This analysis reveals that there are large cost uncertainties associated with all the fuel cycle strategies, and that overall systems (reactor plus fuel cycle) using a closed fuel cycle are about 10% more expensive in terms of electricity generation cost than open cycle systems. The study concludes that further U.S. and joint international-based design studies are needed to reduce the cost uncertainties with respect to fast reactor, fuel separation and fabrication, and waste disposition. The results of this work can help provide insight to the cost-related factors and conditions needed to keep nuclear energy (including closed fuel cycles) economically competitive in the U.S. and worldwide. These results may be updated over time based on new cost information, revised assumptions, and feedback received from additional reviews.
Download or read book יפה שעה written by מכלוף ובחצרה and published by . This book was released on 2002 with total page 336 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Improved Building Methodology and Analysis of Delay Scenarios of Advanced Nuclear Fuel Cycles with the Verifiable Fuel Cycle Simulation Model (VISION). by :
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 and published by . This book was released on 2004 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The goal of this research is to help better understand the areas of uncertainty with advanced nuclear fuel cycles. The Department of Energy has started several large scale programs that will explore and develop advanced nuclear fuel cycle components. One of the key components to this endeavor is a system dynamics model that simulates the construction of nuclear reactors and their required support facilities in a growing energy demand environment. This research developed methods to more accurately determine when to build facilities based upon forecasting methods and inventories. The next phase of the research was to analyze lead times on constructing light water reactor spent fuel separation facilities and possible associated upset events and their mitigation strategies. The results show a smooth building rate for fast burner reactors, which ensures that the reactors will not run out of fuel supply for their entire lifetime. After analyzing several separation facility sizes and variable construction lead times, it was determined that there is an optimal separation facility size and an optimal lead time for a given growth rate for fast reactors. This optimal case kept the separated material inventory at a minimum value, while also building inventories for reactors that are getting ready to begin operation. Upset events were analyzed in order to determine how the system will respond to a separation facility not starting up on time and a separation facility being taken offline. The results show that increasing the lead time on separation facilities is the best way to mitigate a delayed separation facility and decreasing the separation facility size would better mitigate a facility being taken offline. The use of a separated materials fuel bank was also critical in ensuring that no reactors were starved of fuel during these upset events. In conclusion the work done in this thesis helped to create a better understanding for how different facilities interact in an advanced.
Book Synopsis High-fidelity Nuclear Energy System Optimization Towards an Environmentally Benign, Sustainable, and Secure Energy Source by : David Elroy Ames
Download or read book High-fidelity Nuclear Energy System Optimization Towards an Environmentally Benign, Sustainable, and Secure Energy Source written by David Elroy Ames and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A new high-fidelity integrated system method and analysis approach was developed and implemented for consistent and comprehensive evaluations of advanced fuel cycles leading to minimized Transuranic (TRU) inventories. The method has been implemented in a developed code system integrating capabilities of MCNPX for highfidelity fuel cycle component simulations. The impact associated with energy generation and utilization is immeasurable due to the immense, widespread, and myriad effects it has on the world and its inhabitants. The polar extremes are demonstrated on the one hand, by the high quality of life enjoyed by individuals with access to abundant reliable energy sources, and on the other hand by the global-scale environmental degradation attributed to the affects of energy production and use. Thus, nations strive to increase their energy generation, but are faced with the challenge of doing so with a minimal impact on the environment and in a manner that is self-reliant. Consequently, a revival of interest in nuclear energy has followed with much focus placed on technologies for transmuting nuclear spent fuel. In this dissertation, a Nuclear Energy System (NES) configuration was developed to take advantage of used fuel recycling and transmutation capabilities in waste management scenarios leading to minimized TRU waste inventories, long-term activities, and radiotoxicities. The reactor systems and fuel cycle components that make up the NES were selected for their ability to perform in tandem to produce clean, safe, and dependable energy in an environmentally conscious manner. The reactor systems include the AP1000, VHTR, and HEST. The diversity in performance and spectral characteristics for each was used to enhance TRU waste elimination while efficiently utilizing uranium resources and providing an abundant energy source. The High Level Waste (HLW) stream produced by typical nuclear systems was characterized according to the radionuclides that are key contributors to long-term waste management issues. The TRU component of the waste stream becomes the main radiological concern for time periods greater than 300 years. A TRU isotopic assessment was developed and implemented to produce a priority ranking system for the TRU nuclides as related to long-term waste management and their expected characteristics under irradiation in the different reactor systems of the NES. Detailed 3D whole-core models were developed for analysis of the individual reactor systems of the NES. As an inherent part of the process, the models were validated and verified by performing experiment-to-code and/or code-to-code benchmarking procedures, which provided substantiation for obtained data and results. Reactor core physics and material depletion calculations were performed and analyzed. A computational modeling approach was developed for integrating the individual models of the NES. A general approach was utilized allowing for the Integrated System Model (ISM) to be modified in order to provide simulation for other systems with similar attributes. By utilizing this approach, the ISM is capable of performing system evaluations under many different design parameter options. Additionally, the predictive capabilities of the ISM and its computational time efficiency allow for system sensitivity/uncertainty analysis and the implementation of optimization techniques. The NES has demonstrated great potential for providing safe, clean, and secure energy and doing so with foreseen advantages over the LEU once-through fuel cycle option. The main advantages exist due to better utilization of natural resources by recycling the used nuclear fuel, and by reducing the final amount and time span for which the resulting HLW must be isolated from the public and the environment due to radiological hazard. If deployed, the NES can substantially reduce the long-term radiological hazard posed by current HLW, extend uranium resources, and approach the characteristics of an environmentally benign energy system.
Book Synopsis Resonance Region Nuclear Data Analysis to Support Advanced Fuel Cycle Development by :
Download or read book Resonance Region Nuclear Data Analysis to Support Advanced Fuel Cycle Development written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Oak Ridge National Laboratory (ORNL) and the Korean Atomic Energy Research Institute (KAERI) are performing collaborative research as part of a three-year United States (U.S.) / Republic of Korea (ROK) International Nuclear Energy Research Initiative (I-NERI) project to provide improved neutron cross-section data with uncertainty or covariance data important for advanced fuel cycle and nuclear safeguards applications. ORNL and KAERI have initiated efforts to prepare new cross-section evaluations for 240Pu, 237Np, and the stable Cm isotopes. At the current stage of the I-NERI project, ORNL has recently completed a preliminary resonance-region cross-section evaluation with covariance data for 240Pu and initiated resonance evaluation efforts for 237Np and 244Cm. Likewise, KAERI is performing corresponding high-energy cross-section analyses (i.e., above the resonance region) for the noted isotopes. The paper provides results pertaining to the new resonance region evaluation efforts with emphasis on the new 240Pu evaluation.
Book Synopsis A Decision Analysis Framework for the U.S. Nuclear Fuel Cycle by : Lara Marie Pierpoint
Download or read book A Decision Analysis Framework for the U.S. Nuclear Fuel Cycle written by Lara Marie Pierpoint and published by . This book was released on 2011 with total page 224 pages. Available in PDF, EPUB and Kindle. Book excerpt: If we are willing to pay a premium, we may be able to mitigate some of the long-lasting impacts of nuclear waste. Deciding how to navigate this tradeoff, between cost and waste, is a central challenge for stewards of nuclear power. It is made more difficult by uncertainties that characterize the global future of nuclear electricity generation. The recent increase in concern about climate change has prompted U.S. policymakers to back strategies favorable toward nuclear power, so much so that some experts see a "nuclear renaissance" on the horizon. Whether such a renaissance will come to pass, involving the construction of a vast new fleet of nuclear plants, is unclear - especially in light of the March 2011 nuclear accident at the Fukushima Daiichi reactors in Japan. Even more unclear is what should be done with the commercial U.S. nuclear waste, given an array of technical options and a large amount of uncertainty about how much waste will ultimately need to be managed. This study introduces a framework for analysis of strategies to evolve the nuclear fuel cycle which may be helpful in analyzing decision problems for similarly complex, long-lived technical infrastructure systems. The framework consists of a system dynamics simulation coupled with a decision analysis model. The system dynamics code is developed specifically for this study to be simple, fast-running, and also to echo the results of many previous nuclear fuel cycle simulations in demonstrating how various technical options impact important parameters (like uranium consumed, waste generated, etc.). Code results are benchmarked to more complex fuel cycle simulations for the parameters relevant to the decision space. The decision analysis model takes information from the simulation and makes it useful to policymakers, by allowing the explicit analysis of desirable decision pathways under uncertainty, and also considering tradeoffs among system goals. The framework is applied to three nuclear systems, the light-water reactor (LWR) once through fuel cycle, which represents the status quo, an advanced, traditional, plutonium-fed self sustaining fast reactor fuel cycle, and a fast reactor fuel cycle for which initial fast reactor cores are composed of enriched uranium rather than recycled LWR fuel. Fast reactors are highly likely to cost more than LWRs, but they can produce electricity from some of the elements that most plague the long-term management of a nuclear waste repository. A value function compares how these options fare under different scenarios, incorporating system-wide costs and the system waste burden as the two attributes in the function. The primary result is that the best strategy, under a strong preference for eliminating LWR spent nuclear fuel waste, consists of building a few traditional fast reactors now, and then building a full fleet more rapidly later in the century. This allows both for a significant amount of waste mitigation compared to an all-LWR fuel cycle, and for the costs associated with the more expensive fast reactor technology to be incurred primarily later in the century. On the other hand, if cost is the main consideration, the framework advises moving forward with the once-through LWR fuel cycle and avoiding fast reactors altogether, or at least until later in the century. These results are examined from a traditional decision analysis perspective, and then from one that departs somewhat from the assumption of a fully powerful decision maker. In reality, a government decision maker can only offer incentives to industry in order to induce a strategy change. Changing the decision model to reflect this reality causes the framework to more strongly advise moving forward with traditional fast reactors. This occurs because any single attempt at offering incentives to industry might be unsuccessful, and thus prevent a waste concerned government from achieving any significant mitigation. The most important contribution of the methodology is its ability to illuminate which parameters represent strong drivers of system decisions. Preferences across competing attributes are always important: in general, if decision maker preferences for reducing cost vs. waste were to shift significantly, the framework would show a change in the desirable decision strategy. Decision results are not very sensitive, on the other hand, to the rate of nuclear power growth or to the cost of fast reactor technology. A second contribution comes from the initial foray into studying a more complex decision maker perspective, and shows how a different view can complement results using the traditional decision analysis assumption of an "ideal" decision maker. Ultimately, the system dynamics/decision analysis framework presented here helps identify desirable pathways for complex system evolution, identifies factors that bear strongly on decisions and which are deserving of more study, and begins to show how strategy implementation can be considered within the framework in order to further improve decision-making.
Book Synopsis Quantification of Back-end Fuel Cycle Metrics Uncertainties Due to Cross Sections by :
Download or read book Quantification of Back-end Fuel Cycle Metrics Uncertainties Due to Cross Sections written by and published by . This book was released on 2007 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt: Keywords: nuclear fuel cycle, uncertainy analysis, efficient subspace method, cross sections.
Book Synopsis Advanced Fuel Cycle Scenarios with Ap1000 Pwrs and Vhtrs and Fission Spectrum Uncertainties by : Marie-Hermine Cuvelier
Download or read book Advanced Fuel Cycle Scenarios with Ap1000 Pwrs and Vhtrs and Fission Spectrum Uncertainties written by Marie-Hermine Cuvelier and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Minimization of HLW inventories and U consumption are key elements guaranteeing nuclear energy expansion. The integration of complex nuclear systems into a viable cycle yet constitutes a challenging multi-parametric optimization problem. The reactors and fuel cycle performance parameters may be strongly dependent on minor variations in the system's input data. Proven discrepancies in nuclear data evaluations could affect the validity of the system optimization metrics. This study first analyzes various advanced AP1000-VHTR fuel cycle scenarios by assessing their TRU destruction and their U consumption minimization capabilities, and by computing reactor performance parameters such as the time evolution of the effective multiplication factor keff, the reactors' energy spectrum or the isotopic composition/activity at EOL. The performance metrics dependence to prompt neutron fission spectrum discrepancies is then quantified to assess the viability of one strategy. Fission spectrum evaluations are indeed intensively used in reactors' calculations. Discrepancies higher than 10% have been computed among nuclear data libraries for energies above 8MeV for 235U. TRU arising from a 3wt% 235U-enriched UO2-fueled AP1000 were incinerated in a VHTR. Fuels consisting of 20%, 40% and 100% of TRU completed by UO2 were examined. MCNPX results indicate that up to 88.9% of the TRU initially present in a VHTR fueled with 20% of TRU and 80% of ThO2 were transmuted. Additionally, the use of WgPu instead of RgPu should reduce the daily consumption of 235U by 1.3 and augment core lifetime. To estimate the system metrics dependence to fission spectrum discrepancies and validate optimization studies outputs, the VTHR 235U fission spectrum distribution was altered successively in three manners. keff is at worst lowered by 1.7% of the reference value and the energy spectrum by 5% between 50meV and 2MeV when a significantly distorted fission spectrum tail is used. 233U, 236Pu and 237Pu inventories and activities are multiplied by 263, 523 and 34 but are still negligible compared to 239Pu mass or the total activity. The AP1000-VHTR system is in conclusion not dependent on the selected fission spectrum variations. TRU elimination optimization studies in AP1000-VHTR systems will be facilitated by freeing performance metrics dependency from 1 input parameter.
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:
Book Synopsis Best Estimate Safety Analysis for Nuclear Power Plants by :
Download or read book Best Estimate Safety Analysis for Nuclear Power Plants written by and published by . This book was released on 2008 with total page 216 pages. Available in PDF, EPUB and Kindle. Book excerpt: Deterministic safety analysis is an important tool for confirming the adequacy and efficiency of provisions within the defence in depth concept for the safety of nuclear power plants (NPPs). IAEA Safety Standards Series No. NS-R-1.2 and Safety Reports Series No. 23 recommend, as one of the options for demonstrating the inclusion of adequate safety margins, the use of best estimate computer codes with realistic input data in combination with the evaluation of uncertainties in the calculation results. The evaluation of uncertainties is an issue of considerable complexity, and this Safety Report has been developed to complement the existing publications. It provides more detailed information on the methods available for the evaluation of uncertainties in deterministic safety analysis of NPPs and practical guidance in the use of these methods.
