Read Books Online and Download eBooks, EPub, PDF, Mobi, Kindle, Text Full Free.
Nuclear Fuel Cycle Optimization
Download Nuclear Fuel Cycle Optimization full books in PDF, epub, and Kindle. Read online Nuclear Fuel Cycle Optimization ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!
Book Synopsis Nuclear Fuel Cycle Optimization by : P. Silvennoinen
Download or read book Nuclear Fuel Cycle Optimization written by P. Silvennoinen and published by Elsevier. This book was released on 2013-10-22 with total page 139 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear Fuel Cycle Optimization: Methods and Modelling Techniques discusses applicable methods for analysis of fuel cycle logistics and optimization and evaluation of the economics of various reactor strategies. The opening chapter covers the nuclear fuel cycle, while the next chapter tackles uranium supply and demand. Chapter 3 discusses basic model of the light water reactor (LWR). The fourth chapter talks about the resolution of uncertainties, and the fifth chapter discusses the assessment of proliferation risks. Chapter 6 covers multigoal optimization, while Chapter 7 deals with the generalized fuel cycle models. The eighth chapter covers reactor strategy calculations, whereas the last chapter discusses interface with energy strategy. The book will appeal to students of energy economics or of nuclear engineering.
Book Synopsis Sensitivity Analysis and Optimization of the Nuclear Fuel Cycle by : Stefano Passerini
Download or read book Sensitivity Analysis and Optimization of the Nuclear Fuel Cycle written by Stefano Passerini and published by . This book was released on 2012 with total page 309 pages. Available in PDF, EPUB and Kindle. Book excerpt: For decades, nuclear energy development was based on the expectation that recycling of the fissionable materials in the used fuel from today's light water reactors into advanced (fast) reactors would be implemented as soon as technically feasible in order to extend the nuclear fuel resources. More recently, arguments have been made for deployment of fast reactors in order to reduce the amount of higher actinides, hence the longevity of radioactivity, in the materials destined to a geologic repository. The cost of the fast reactors, together with concerns about the proliferation of the technology of extraction of plutonium from used LWR fuel as well as the large investments in construction of reprocessing facilities have been the basis for arguments to defer the introduction of recycling technologies in many countries including the US. In this thesis, the impacts of alternative reactor technologies on the fuel cycle are assessed. Additionally, metrics to characterize the fuel cycles and systematic approaches to using them to optimize the fuel cycle are presented. The fuel cycle options of the 2010 MIT fuel cycle study are re-examined in light of the expected slower rate of growth in nuclear energy today, using the CAFCA (Code for Advanced Fuel Cycle Analysis). The Once Through Cycle (OTC) is considered as the base-line case, while advanced technologies with fuel recycling characterize the alternative fuel cycle options available in the future. The options include limited recycling in LWRs and full recycling in fast reactors and in high conversion LWRs. Fast reactor technologies studied include both oxide and metal fueled reactors. Additional fuel cycle scenarios presented for the first time in this work assume the deployment of innovative recycling reactor technologies such as the Reduced Moderation Boiling Water Reactors and Uranium-235 initiated Fast Reactors. A sensitivity study focused on system and technology parameters of interest has been conducted to test the robustness of the conclusions presented in the MIT Fuel Cycle Study. These conclusions are found to still hold, even when considering alternative technologies and different sets of simulation assumptions. Additionally, a first of a kind optimization scheme for the nuclear fuel cycle analysis is proposed and the applications of such an optimization are discussed. Optimization metrics of interest for different stakeholders in the fuel cycle (economics, fuel resource utilization, high level waste, transuranics/proliferation management, and environmental impact) are utilized for two different optimization techniques: a linear one and a stochastic one. Stakeholder elicitation provided sets of relative weights for the identified metrics appropriate to each stakeholder group, which were then successfully used to arrive at optimum fuel cycle configurations for recycling technologies. The stochastic optimization tool, based on a genetic algorithm, was used to identify non-inferior solutions according to Pareto's dominance approach to optimization. The main tradeoff for fuel cycle optimization was found to be between economics and most of the other identified metrics.
Book Synopsis Optimization of Nuclear Fuel Cycle Strategies Under Uncertainty by : Juhani Vira
Download or read book Optimization of Nuclear Fuel Cycle Strategies Under Uncertainty written by Juhani Vira and published by . This book was released on 1981 with total page 42 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis NUFCOS - Nuclear Fuel Cycle Optimization System by :
Download or read book NUFCOS - Nuclear Fuel Cycle Optimization System written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Out-of-core Nuclear Fuel Cycle Economic Optimization for Nonedquilibrium Cycles by : Scott A. Comes
Download or read book Out-of-core Nuclear Fuel Cycle Economic Optimization for Nonedquilibrium Cycles written by Scott A. Comes and published by . This book was released on 1987 with total page 388 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fuel Cycle Optimization of Thorium and Uranium Fueled PWR Systems by : Keith Courtnay Garel
Download or read book Fuel Cycle Optimization of Thorium and Uranium Fueled PWR Systems written by Keith Courtnay Garel and published by . This book was released on 1977 with total page 296 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Optimization of Material Flow in the Nuclear Fuel Cycle Using a Cyclic Multi-stage Production-to-inventory Model by : Elden Leo DePorter
Download or read book Optimization of Material Flow in the Nuclear Fuel Cycle Using a Cyclic Multi-stage Production-to-inventory Model written by Elden Leo DePorter and published by . This book was released on 1977 with total page 390 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Multi-cycle Boiling Water Reactor Fuel Cycle Optimization by : Keith Everette Ottinger
Download or read book Multi-cycle Boiling Water Reactor Fuel Cycle Optimization written by Keith Everette Ottinger and published by . This book was released on 2014 with total page 140 pages. Available in PDF, EPUB and Kindle. Book excerpt: A multi-cycle nuclear fuel cycle optimization code, BWROPT (Boiling Water Reactor OPTimization), has been developed. BWROPT uses the Parallel Simulated Annealing (PSA) algorithm to solve the coupled out-of-core and in-core optimization problems. There are two depletion methods used for the in-core optimization: the Haling depletion and a Control Rod Pattern (CRP) search. The result of this optimization is the optimum new fuel inventory and the core loading pattern for the first cycle considered in the optimization. Several changes were made to the optimization algorithm with respect to other nuclear fuel cycle optimization codes that use PSA. Instead of using constant sampling probabilities for the solution perturbation types throughout the optimization, as is usually done, the sampling probabilities can be varied to get a better solution and/or decrease runtime. Also, the new fuel types available for use can be sorted into an array based on any parameter so that each parameter can be incremented or decremented. In addition several evaluations were performed to test the CRP search option. Using the variable sampling probabilities was found to produce slightly better results in less time than the standard method of having constant sampling probabilities. Performing ordered and random sampling of the new fuel types using the new fuel type array was found to yield slightly better solutions on average than random sampling alone, but with a somewhat higher runtime. Using variable length Markov chains for optimizations in which a CRP search is performed for the first cycle and the Haling depletion is used for the remaining cycles was found to increase CPU utilization by 33%. Starting the CRP search with the CRP determined for the previous solution was found to be better than starting the CRP search with all of the rods fully withdrawn. Using the CRP search in an optimization was slow and produced inferior results compared to using the Haling depletion, indicating the need for more work in this area.
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 Optimization of Safeguards for a Low-enriched Uranium Fuel Cycle by : Anita Nilsson
Download or read book Optimization of Safeguards for a Low-enriched Uranium Fuel Cycle written by Anita Nilsson and published by . This book was released on 1992 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fuel Management and Load Optimization for Nuclear Power Plants in Electric Utility Systems by : Arturo Guillermo Reinking-Cejudo
Download or read book Fuel Management and Load Optimization for Nuclear Power Plants in Electric Utility Systems written by Arturo Guillermo Reinking-Cejudo and published by . This book was released on 1974 with total page 456 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Argentine-German co-operation on fuel cycle optimization for the Nuclear Power Plant Atucha by : Hans-Jürgen Zech
Download or read book Argentine-German co-operation on fuel cycle optimization for the Nuclear Power Plant Atucha written by Hans-Jürgen Zech and published by . This book was released on 1975 with total page 58 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis A Generalized Optimization Methodology for Isotope Management by : Mark Edward Massie
Download or read book A Generalized Optimization Methodology for Isotope Management written by Mark Edward Massie and published by . This book was released on 2010 with total page 97 pages. Available in PDF, EPUB and Kindle. Book excerpt: This research, funded by the Department of Energy's Advanced Fuel Cycle Initiative Fellowship, was focused on developing a new approach to studying the nuclear fuel cycle: instead of using the trial and error approach currently used in actinide management studies in which reactors are designed and then their performance is evaluated, the methodology developed here first identified relevant fuel cycle objectives like minimizing decay heat production in a repository, minimizing Pu-239 content in used fuel, etc. and then used optimization to determine the best way to reach these goals. The first half of this research was devoted to identifying optimal flux spectra for irradiating used nuclear fuel from light water reactors to meet fuel cycle objectives like those mentioned above. This was accomplished by applying the simulated annealing optimization methodology to a simple matrix exponential depletion code written in Fortran using cross sections generated from the SCALE code system. Since flux spectra cannot be shaped arbitrarily, the second half of this research applied the same methodology to material composition of fast reactor target assemblies to find optimal designs for minimizing the integrated decay heat production over various timescales. The neutronics calculations were performed using modules from SCALE and ERANOS, a French fast reactor transport code. The results of this project showed that a thermal flux spectrum is much more effective for transmuting used nuclear fuel. In the spectral optimization study, it was found that a thermal flux spectrum is approximately five times more effective at reducing long-term decay heat production than a fast flux spectrum. This conclusion was reinforced by the results of the target assembly material optimization study, which found that by adding an efficient moderator to a target assembly designed for minor actinide transmutation, the amount of decay heat generated over 10,000 years of cooling can be reduced by over 50% through a single pass in a fast reactor without exceeding standard cladding fluence limits.
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 Development and Utilization of Mathematical Optimization in Advanced Fuel Cycle Systems Analysis by :
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.
Book Synopsis A Computer Simulation and Optimization of the Total Fuel Costs Due to the Front End of the Nuclear Fuel Cycle by : Duane E. Gore
Download or read book A Computer Simulation and Optimization of the Total Fuel Costs Due to the Front End of the Nuclear Fuel Cycle written by Duane E. Gore and published by . This book was released on 1987 with total page 146 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis The Change of Paradigm in Nuclear Fuel Optimization by : Sergey Pelykh
Download or read book The Change of Paradigm in Nuclear Fuel Optimization written by Sergey Pelykh and published by Cambridge Scholars Publishing. This book was released on 2019-03-21 with total page 210 pages. Available in PDF, EPUB and Kindle. Book excerpt: This monograph highlights pertinent problems in nuclear fuel optimization. It shows that the current approach does not allow us to predict the synergic effects leading to fuel-related accidents, and is characterized by great uncertainty with regards to estimating fuel cladding failure conditions and the reduced efficiency of fuel operation. The book describes in detail a new philosophy of nuclear fuel optimization based on the synergic paradigm, applicable to both operating and prospective reactors, in order to minimize radioactive leakage under normal and emergency fuel operating conditions, to resolve the safety-efficiency contradiction for nuclear fuel operation, and to predict new synergic effects due to processes of self-organization in the reactor core. It will appeal to researchers, academics, PhD students and engineers engaged in developing prospective nuclear reactor designs, as well as those who verify the safety and efficiency of nuclear fuel operation under increasingly challenging core conditions.