دانلود کتاب تاریخچه، فناوری‌ها و درس‌های توسعه راکتور هسته‌ای

This book investigates, compiles, and discusses the history and lessons of the research and development of power reactors worldwide from the dawn of nuclear energy use to the present, based on reports from Western government agencies and others.
The development of reactors for the use of nuclear energy for power generation and propulsion was actively carried out in the United States after World War II. The military, the Department of Energy, and companies built various test reactors and power reactors. Not only light water reactors, but also what are now called new types of reactors, most of them have their roots in these. The Pressurized Water Reactor (PWR) was developed based on a submarine reactor, and the Boiling Water Reactor (BWR) was developed by an American electric company in search of a type of light water reactor different from the pressurized water reactor. For testing purposes, the U.S. Department of Energy built a nuclear reactor test site in the desert of Idaho. Various types of reactors are being tested, not only for power generation but also for aircraft and space propulsion, marine use, and remote power sources. In the UK, France, Canada, and the Soviet Union, unique power-generating nuclear reactors were developed.
Understanding the history and lessons of research and development of power-generating nuclear reactors is as important as studying nuclear reactor physics and heat transfer fluid engineering. However, while there are books that describe the structure, dimensions, and design standards of light water reactors, it is rare to find ones that describe the history and circumstances leading up to them, not as a story, but as a record. The experiences of accidents and troubles with early light water reactor test reactors and prototype reactors are reflected in the design of the light water reactors currently in use. Those who started using light water reactors in Japan had heard about the experiences and design changes in the early stages of light water reactor development when they built and operated the first power-generating units of the Power Reactor (JPDR), PWR, and BWR, and they had that knowledge. However, they are no longer with us, so we cannot ask them about their experiences. Not only the reactors themselves, but also the technologies used in power-generating nuclear reactors have been improved and advanced. These include nuclear fuel, instrumenta-tion and control technology, and nuclear reactor analysis technology. Improvements to enhance passive safety to reduce dependence on power-requiring active equip-ment, and measures against core meltdown accidents, have been researched and developed worldwide since the Chernobyl accident. This book will also introduce these technologies and developments.
Currently, light water reactors have become the mainstream of power-generating nuclear reactors, but various types of power-generating nuclear reactors were devel-oped and used worldwide. These include the Heavy Water-Moderated Reactor (CANDU) developed by Canada, the Graphite-Moderated Carbon Dioxide-Cooled Reactor developed by the UK and France, the High-Temperature Gas Reactor of the United States and West Germany, the Graphite-Moderated Boiling Light Water-Cooled Pressure Tube Reactor (RBMK) of the former Soviet Union, and the Liquid Metal-Cooled Fast Reactor developed in many countries. Some of these are still in use and being researched and developed. Furthermore, although they have not yet reached full practical use, liquid fuel reactors, molten salt reactors, organic material-cooled reactors, and nuclear reactors for aerospace use have also been researched and tested. Among these, there are similar types that are being discussed in research and development as new types of reactors. Knowing the history of these reactor types, and the lessons and challenges of their development, is necessary to broaden the perspective on power-generating nuclear reactors, recognize the challenges, and plan for the future.
Around the year 2000, under the leadership of the United States, practical applica-tions were made toward the construction of generation three (Generation III) nuclear reactors, and research and development programs for generation four (Generation IV) nuclear reactors were conducted. The supercritical pressure light water reactor (SCWR) that the author researched at a university from the late 1980s was selected as a Generation IV nuclear reactor and was researched worldwide. The author intro-duced this experience in this book because he thought it would be a reference for the future. Since being appointed as the Chairman of Japan Atomic Energy Commis-sion of Japanese government in 2014, the author has shifted his focus and interest to the issues at the intersection of nuclear power generation and society, and has not conducted research on SCWR.