Author: Mohamed A. ElmaghrabiPublisher:
ISBN:
Category :
Languages : en
Pages : 222
Book Description
Nuclear Reactor Core Fuel Cycle Analysis and Computation for Pressurized Water Reactors
Author: Mohamed A. ElmaghrabiPublisher:
ISBN:
Category :
Languages : en
Pages : 222
Book Description
Nuclear Reactor Design
Author: Yoshiaki OkaPublisher: Springer
ISBN: 443154898X
Category : Technology & Engineering
Languages : en
Pages : 337
Book Description
This book focuses on core design and methods for design and analysis. It is based on advances made in nuclear power utilization and computational methods over the past 40 years, covering core design of boiling water reactors and pressurized water reactors, as well as fast reactors and high-temperature gas-cooled reactors. The objectives of this book are to help graduate and advanced undergraduate students to understand core design and analysis, and to serve as a background reference for engineers actively working in light water reactors. Methodologies for core design and analysis, together with physical descriptions, are emphasized. The book also covers coupled thermal hydraulic core calculations, plant dynamics, and safety analysis, allowing readers to understand core design in relation to plant control and safety.
Optimization of In-core Nuclear Fuel Management in a Pressurized Water Reactor
Author: Richard Bartholomew StoutPublisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 316
Book Description
Fuel loading patterns which have a minimum power peak are economically desirable to allow power reactors to operate at the highest possible power density and to minimize the possibility of fuel failure. A computer code called SHUFLE was developed for pressurized water reactors which shuffles the fuel in search of the lowest possible power peaking factor. An iterative approach is used in this search routine. A radial power distribution is calculated from which the program logic Selects a movement of fuel elements in an attempt to lower the radial power peak. Another power calculation is made and the process repeated until a predetermined convergence is reached. The logic by which the code decides the fuel movement is presented, along with the criteria for accepting or rejecting the move after a power calculation of the new loading pattern is made. A 1.5 group course mesh diffusion theory method was used to obtain the power distribution for each SHUFLE iteration. Convergence to a final loading pattern varies from about 10 to 40 shuffling iterations depending on the initial loading presented to the code. Since the typical computer running time for a one-quarter core power distribution with this 1.5 group method is only one to a few seconds, depending on the loading, convergence to a good loading pattern takes on the order of one minute on a Univac 1108. The low computer cost plus ease of operation should make this code of considerable use in determining loading patterns with minimum power peaking for any given set of fuel elements. The program also has burnup capability which can be used to check power peaking throughout core life. A parametric analysis study of fuel cycle costs for a PWR is also presented. Cost parameters analyzed were variation in the cost of yellow cake, enrichment, money, fabrication, and reprocessing plus changes in burnup, load factors, power densities, and the effect of forced early discharge. Figures are presented to indicate total fuel costs as a function of burnup for these cost parameters. Linear relationships for minimum cost and optimum burnup are presented for each parameter.
The Linear Reactivity Model for Nuclear Fuel Management
Author: M. J. DriscollPublisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 264
Book Description
The Linear Reactivity Model (LRM) is a simple nuclear fuel management model that comes with a diskette containing three programs. Consisting of a collection of algorithms and methods, the LRM describes complex core behavior, but it is simpler than the complex programs developed for design calculations. This makes the LRM particularly useful as a teaching tool to explain the basic principles of nuclear fuel management. The LRM mainly focuses on the pressurized water reactor, but it is also directly applicable to the boiling water reactor. Application of the LRM to the CANDU reactor is also covered.
Thermal Analysis of Pressurized Water Reactors
Author: Long-sun TongPublisher:
ISBN:
Category : Science
Languages : en
Pages : 776
Book Description
The basic objective of this book is to present the principles underlying the thermal and hydraulic design of pressurized water reactors. In addition, the empirical data, engineering properties, and computer techniques required for design, but not available in conventional handbooks, are presented or referenced. Because of the many advances and changes that have occurred since the second edition, extensive improvements in both understanding the phenomena involved and in calculational techniques are reflected in the substantial additions to this third edition. Also, an additional chapter has been added to accommodate the many developments in the area of safety analysis.
Non-Proliferative, Thorium-Based, Core and Fuel Cycle for Pressurized Water Reactors
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Two of the major barriers to the expansion of worldwide adoption of nuclear power are related to proliferation potential of the nuclear fuel cycle and issues associated with the final disposal of spent fuel. The Radkowsky Thorium Fuel (RTF) concept proposed by Professor A. Radkowsky offers a partial solution to these problems. The main idea of the concept is the utilization of the seed-blanket unit (SBU) fuel assembly geometry which is a direct replacement for a 'conventional' assembly in either a Russian pressurized water reactor (VVER-1000) or a Western pressurized water reactor (PWR). The seed-blanket fuel assembly consists of a fissile (U) zone, known as seed, and a fertile (Th) zone known as blanket. The separation of fissile and fertile allows separate fuel management schemes for the thorium part of the fuel (a subcritical 'blanket') and the 'driving' part of the core (a supercritical 'seed'). The design objective for the blanket is an efficient generation and in-situ fissioning of the U233 isotope, while the design objective for the seed is to supply neutrons to the blanket in a most economic way, i.e. with minimal investment of natural uranium. The introduction of thorium as a fertile component in the nuclear fuel cycle significantly reduces the quantity of plutonium production and modifies its isotopic composition, reducing the overall proliferation potential of the fuel cycle. Thorium based spent fuel also contains fewer higher actinides, hence reducing the long-term radioactivity of the spent fuel. The analyses show that the RTF core can satisfy the requirements of fuel cycle length, and the safety margins of conventional pressurized water reactors. The coefficients of reactivity are comparable to currently operating VVER's/PWR's. The major feature of the RTF cycle is related to the total amount of spent fuel discharged for each cycle from the reactor core. The fuel management scheme adopted for RTF core designs allows a significant decrease in the amount of discharged spent fuel, for a given energy production, compared with standard VVER/PWR. The total Pu production rate of RTF cycles is only 30 % of standard reactor. In addition, the isotopic compositions of the RTF's and standard reactor grade Pu are markedly different due to the very high burnup accumulated by the RTF spent fuel.
Nuclear Fuel Cycle Optimization
Author: P. SilvennoinenPublisher: Elsevier
ISBN: 1483145549
Category : Technology & Engineering
Languages : en
Pages : 139
Book Description
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.
Fuel Cycle Program - a Boiling Water Reactor Research and Development Program
Author: Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 64
Book Description
Advances in Nuclear Science and Technology
Author: Jeffery LewinsPublisher: Springer Science & Business Media
ISBN: 1461399254
Category : Science
Languages : en
Pages : 239
Book Description
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.
Author: