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The conceptual design of a low cost training reactor for the instruction of physicists and engineers is covered. It is conceived as an instructional tool for a course such as that given at the Oak Ridge School of Reactor Technology. The reactor is of a modified pool type, and is designed for a maximum power level of one Mw. This arrangement will accommodate engineering experiments, shielding experiments, and critical experiments as well as being useful as a neutron and gamma source. (auth).
An introductory text for broad areas of nuclear reactor physics Nuclear Reactor Physics and Engineering offers information on analysis, design, control, and operation of nuclear reactors. The author—a noted expert on the topic—explores the fundamentals and presents the mathematical formulations that are grounded in differential equations and linear algebra. The book puts the focus on the use of neutron diffusion theory for the development of techniques for lattice physics and global reactor system analysis. The author also includes recent developments in numerical algorithms, including the Krylov subspace method, and the MATLAB software, including the Simulink toolbox, for efficient studies of steady-state and transient reactor configurations. In addition, nuclear fuel cycle and associated economics analysis are presented, together with the application of modern control theory to reactor operation. This important book: Provides a comprehensive introduction to the fundamental concepts of nuclear reactor physics and engineering Contains information on nuclear reactor kinetics and reactor design analysis Presents illustrative examples to enhance understanding Offers self-contained derivation of fluid conservation equations Written for undergraduate and graduate students in nuclear engineering and practicing engineers, Nuclear Reactor Physics and Engineering covers the fundamental concepts and tools of nuclear reactor physics and analysis.
Fundamentals of Nuclear Reactor Physics offers a one-semester treatment of the essentials of how the fission nuclear reactor works, the various approaches to the design of reactors, and their safe and efficient operation . It provides a clear, general overview of atomic physics from the standpoint of reactor functionality and design, including the sequence of fission reactions and their energy release. It provides in-depth discussion of neutron reactions, including neutron kinetics and the neutron energy spectrum, as well as neutron spatial distribution. It includes ample worked-out examples and over 100 end-of-chapter problems. Engineering students will find this applications-oriented approach, with many worked-out examples, more accessible and more meaningful as they aspire to become future nuclear engineers. A clear, general overview of atomic physics from the standpoint of reactor functionality and design, including the sequence of fission reactions and their energy release In-depth discussion of neutron reactions, including neutron kinetics and the neutron energy spectrum, as well as neutron spatial distribution Ample worked-out examples and over 100 end-of-chapter problems Full Solutions Manual
The Kyoto University critical assembly is recognized as one of the most remarkable research reactors in the world to conduct basic experimental research in nuclear reactor physics. This textbook is based on the "Joint Laboratory Reactor Course for Students," carried out over 35 years in the Kyoto University Critical Assembly (KUCA). The book is edited as an international nuclear education and training course for all students and engineers from all over the world majoring in nuclear engineering. It covers indispensable topics, including approach to criticality, control rod calibration, and several reactor parameter measurements. Furthermore, it serves as a key reference for the main basis of nuclear education and training in Asia.
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.
The Nuclear Engineering and Engineering Physics Department of the University of Virginia was awarded a grant by the US Department of Energy in 1984 to establish and administer a reactor operator training program for disadvantaged Americans. Stipends were provided by the US DOE for five trainees with the anticipation that four other educational facilities would participate in the program. Sub-contracts were awarded to four other Universities: Massachusetts Institute of Technology, The University of Missouri at Columbia, Oregon State University, and The State University of New York at Buffalo. The initial two year program was very successful and the grant was renewed in late 1986 for another two years. MIT declined to participate in the second program and was replaced by Ohio State University. U. VA. was notified in September, 1987 that new funding would no longer be provided for this program after December, 1987. U. VA. requested and was granted a no cost extention for the program through December, 1990, since sufficient funds remained in the initial grant to pursue the program further. DOE subsequently approved a no cost extension through November, 1992.