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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.
"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.
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.
Describes the rationale and vision for the peaceful use of nuclear energy. The publication identifies the basic principles that nuclear energy systems must satisfy to fulfil their promise of meeting growing global energy demands.
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.
This book covers the fundamentals of thermodynamics required to understand electrical power generation systems, honing in on the application of these principles to nuclear reactor power systems. It includes all the necessary information regarding the fundamental laws to gain a complete understanding and apply them specifically to the challenges of operating nuclear plants. Beginning with definitions of thermodynamic variables such as temperature, pressure and specific volume, the book then explains the laws in detail, focusing on pivotal concepts such as enthalpy and entropy, irreversibility, availability, and Maxwell relations. Specific applications of the fundamentals to Brayton and Rankine cycles for power generation are considered in-depth, in support of the book’s core goal- providing an examination of how the thermodynamic principles are applied to the design, operation and safety analysis of current and projected reactor systems. Detailed appendices cover metric and English system units and conversions, detailed steam and gas tables, heat transfer properties, and nuclear reactor system descriptions.
Reports the results of an IAEA coordinated research project on patient dose optimization in fluoroscopically guided interventional procedures. The summary presents information on the assessment of high skin doses, analyses the factors causing radiation skin injury and makes recommendations on how to reduce the likelihood of such complications.
The editors are happy to present the twentieth volume in the review series Advances in Nuclear Science and Technology. Lahey and Drew, our first authors, present a concise development of the equations for two-phase flow, essential to the understanding of normal and, even more, accidental behavior in water-cooled reactors. The commitment to the PWR in Europe (now joined by England in this respect) and the aftermath of Chernobyl in the U.S.S.R. put continuing emphasis on the need for good understanding of two-phase phenomena to provide good modelling. The second review, by Downar and Sesonske, of light water reactor fuel modelling, follows this LWR interest and emphasises a current major economic interest: how to get the most out of fuel. Recollecting that the capital cost of nuclear power is high, it is easy to overlook the fact that in the lifetime of a plant as much money is spent on fuel as capital. Optimization is worthwhile. The U.S. scene still does not practice recycling whereas the European scene does. Now that the United Kingdom is building its first (commercial) light water reactor, the linear modelling of burnup exploited by the second authors will prove even more useful, although previously exploited for advanced gas-cooled reactors. If the U.K. is behind in this respect, the recycling undertaken by France and England has led to trial use of plutonium in thermal reactors but, even more, the availability of plutonium for fast reactors.