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INTRODUCTION TO NUCLEAR REACTOR PHYSICS is the most comprehensive, modern and readable textbook for this course/module. It explains reactors, fuel cycles, radioisotopes, radioactive materials, design, and operation. Chain reaction and fission reactor concepts are presented, plus advanced coverage including neutron diffusion theory. The diffusion equation, Fisk's Law, and steady state/time-dependent reactor behavior. Numerical and analytical solutions are also covered. The text has full color illustrations throughout, and a wide range of student learning features.

The Department of Energy's (DOE) Office of Nuclear Energy's (NE) approach to advanced reactor research and development (R&D) focuses on three reactor technologies—high-temperature gas-cooled reactors, sodium-cooled fast reactors, and fluoride-salt-cooled high-temperature reactors—but NE is also funding research into other advanced reactor technologies. NE's approach is to conduct research in support of multiple advanced reactor technologies, while collaborating with industry and academia, with the ultimate goal for industry to take the results of NE's research to the next step of development and commercialization. This book describes NE's approach to advanced nuclear reactor R&D and examines how NE plans and prioritizes its advanced reactor R&D activities, including deploying an advanced reactor. This book also discusses the DOE's International Thermonuclear Experimental Reactor (ITER) Agreement. It examines how and why the estimated costs and schedule of the U.S. ITER Project have changed since 2006; the reliability of DOE's current cost and schedule estimates; and actions DOE has taken to reduce U.S. ITER Project costs and plan for their impact on the overall U.S. fusion program.

Proceedings of the Wingspread Conference on Advanced Converters and Near Breeders

A major concern about the global expansion of nuclear power is the potential spread of nuclear fuel cycle technology (particularly uranium enrichment and spent fuel processing) that could be used for nuclear weapons. Despite 30 years of effort to limit access to uranium enrichment, several undeterred states pursued clandestine nuclear programs, the A.Q. Khan black market network's sales to Iran and North Korea representing the most egregious examples. However, concern over the spread of enrichment and reprocessing technologies may be offset by support for nuclear power as a cleaner and more secure alternative to fossil fuels. This book explores the history of reactor and fuel cycle technologies development with a focus on the policy implications of expanding global access to nuclear power and U.S. uranium reserve estimates.

Chapter 1 - Semi–empirical Mass Formula and Nuclear Shell Model Chapter 2 - Radioactive Decay Chapter 3 - Nuclear Fusion Chapter 4 - Nuclear Fission Chapter 5 - Nucleon Chapter 6 - Nuclear Engineering Chapter 7 - Neutron Moderator Chapter 8 - Nuclear Criticality Safety and Atomic Battery Chapter 9 - Nuclear Fuel Cycle Chapter 10 - Critical Mass Chapter 11 - Neutron Poison and Neutron Source Chapter 12 - Nuclear Decommissioning Chapter 13 - Long–lived Fission Product and Nuclear Fusion-Fission Hybrid Chapter 14 - Prompt Neutron and Prompt Critical

Reactor Operation covers the theoretical aspects and design information of nuclear reactors. This book is composed of nine chapters that also consider their control, calibration, and experimentation. The opening chapters present the general problems of reactor operation and the principles of reactor control and operation. The succeeding chapters deal with the instrumentation, start-up, pre-commissioning, and physical experiments of nuclear reactors. The remaining chapters are devoted to the control rod calibrations and temperature coefficient measurements in the reactor. These chapters also explore the fuel leak detection and fuel movement in the nuclear reactor. This book will prove useful to nuclear engineers, physicists, and undergraduate and postgraduate students.

Progress in Nuclear Energy, Volume 5 covers the significant advances in several aspects of nuclear energy field. This book is composed six chapters that describe the progress in nuclear and gas-cooled reactors. The introductory chapter deals with the development and evolution of decay heat estimates and decay heat Standards, and illustrates the use of these estimates through comparison of both the actinide and fission product decay heat levels from typical fuel samples in a variety of reactor systems. The succeeding chapters present different practical methods for handling resonance absorption problem in the case of thermal reactor lattices and review the physics of the different noise phenomena. These topics are followed by discussions of the developed methodology for the description of breeding, conversion, long-term fuel logistics, and related subjects derived from the detailed mathematical description of the fuel cycle. The concluding chapters consider the historical development of heat transfer surfaces for gas-cooled reactors. These chapters also provide a complete set of differential nuclear data on the three technologically important americium isotopes, 241Am, 242Am, and 243Am, suitable for incorporation into the computer-based U.K. Nuclear Data Library. This book will prove useful to nuclear physicists and nuclear energy scientists and researchers.

An Introduction to the Neutron Kinetics of Nuclear Power Reactors introduces the reader to the neutron kinetics of nuclear power reactors. Topics covered include the neutron physics of reactor kinetics, feedback effects, water-moderated reactors, fast reactors, and methods of plant control. The reactor transients following faults are also discussed, along with the use of computers in the study of power reactor kinetics. This book is comprised of eight chapters and begins with an overview of the reactor physics characteristics of a nuclear power reactor and their influence on system design and operation. The use of a mathematical model of the system to study reactor kinetics and control is described. The following chapters explore the neutronic aspects of reactor kinetics; the interaction between neutronic events and the behavior of other physical quantities of the reactor; the influence of feedback effects on neutron kinetics; and the neutron kinetics of water-moderated reactors and fast reactors. The different control schemes for nuclear power reactors are also considered. The final chapter looks at the use of computers to solve the equations of kinetic models for nuclear power reactors. This monograph will be a useful resource for nuclear scientists, physicists, and engineers.