Closed Nuclear Fuel Cycle With Fast Reactors

Closed Nuclear Fuel Cycle with Fast Reactors: Handbook of Russian Nuclear Power provides unique insights into research and practical activities from leading Russian experts. It presents readers with unprecedented insight and essential knowledge surrounding nuclear fast reactor technologies, as well as novel methods to close the nuclear fuel cycle to achieve cleaner, more environmentally friendly, and more efficient nuclear power. Using the Proryv Project as a framework, the book's contributors provide detailed descriptions of technologies in development in Russia, allowing readers from around the globe to gain a thorough understanding which they can then apply to their own research and practice. Nuclear engineers and technologists of fast reactors, advanced reactors and fuel cycles will use this book as a guide to inform new technology development. They will be able to use the experiences from the Proryv Project to drive fast reactor development with closed fuel cycles for the future. Provides a presentation of new nuclear reactor and fuel cycle technologies within the unique framework of Russia’s Proryv Project Presents novel technologies to close the nuclear fuel cycle to promote cleaner and more environmentally protective nuclear power Includes thorough coverage on the topic, including core design, coolants, fuels, accident protection and waste management technologies

Sodium Fast Reactors with Closed Fuel Cycle delivers a detailed discussion of an important technology that is being harnessed for commercial energy production in many parts of the world. Presenting the state of the art of sodium-cooled fast reactors with closed fuel cycles, this book:Offers in-depth coverage of reactor physics, materials, design, s

This publication reports the results of an evaluation of nuclear energy systems based on a closed nuclear fuel cycle with fast reactors (CNFC-FR). The study was carried out by an international group of experts from Canada, China, France, India, Japan, the Republic of Korea, the Russian Federation and Ukraine, using an assessment methodology developed by International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). The INPRO methodology takes a holistic approach to assess innovative nuclear energy systems in seven areas: economics, infrastructure, safety, waste management, environment, proliferation resistance and physical protection. The study concluded that all INPRO requirements for a sustainable nuclear energy system are fulfilled by the assessed CNFC-FR except in the area of economics, where ongoing R&D programs will provide further insights to bridge knowledge gaps. The full report is available on the accompanying CD

The Generation IV Forum is an international nuclear energy research initiative aimed at developing the fourth generation of nuclear reactors, envisaged to enter service halfway the 21st century. One of the Generation IV reactor systems is the Gas Cooled Fast Reactor (GCFR), the subject of study in this thesis. The Generation IV reactor concepts should improve all aspects of nuclear power generation. Within Generation IV, the GCFR concept specifically targets sustainability of nuclear power generation. The Gas Cooled Fast Reactor core power density is high in comparison to other gas cooled reactor concepts. Like all nuclear reactors, the GCFR produces decay heat after shut down, which has to be transported out of the reactor under all circumstances. The layout of the primary system therefore focuses on using natural convection Decay Heat Removal (DHR) where possible, with a large coolant fraction in the core to reduce friction losses.

What Is Thorium Fuel Cycle The fertile material in the thorium fuel cycle is an isotope of thorium called 232Th, and the thorium fuel cycle itself is a kind of nuclear fuel cycle. Within the reactor, 232Th is converted into the fissile artificial uranium isotope 233U, which is then used as the fuel for the nuclear reactor. Natural thorium, in contrast to natural uranium, only contains minute quantities of fissile material, which is insufficient to kick off a nuclear chain reaction. In order to kickstart the fuel cycle, either more fissile material or an other neutron source is required. 233U is created when 232Th, which is powered by thorium, absorbs neutrons in a reactor. This is analogous to the process that occurs in uranium breeder reactors, in which fertile 238U is subjected to neutron absorption in order to produce fissile 239Pu. The produced 233U either fissions in situ or is chemically removed from the old nuclear fuel and converted into new nuclear fuel, depending on the architecture of the reactor and the fuel cycle. Fissioning in situ is the more efficient method. How You Will Benefit (I) Insights, and validations about the following topics: Chapter 1: Thorium fuel cycle Chapter 2: Nuclear reactor Chapter 3: Radioactive waste Chapter 4: Fissile material Chapter 5: Nuclear fuel cycle Chapter 6: MOX fuel Chapter 7: Breeder reactor Chapter 8: Uranium-238 Chapter 9: Energy amplifier Chapter 10: Subcritical reactor Chapter 11: Integral fast reactor Chapter 12: Fertile material Chapter 13: Uranium-233 Chapter 14: Plutonium-239 Chapter 15: Isotopes of uranium Chapter 16: Isotopes of plutonium Chapter 17: Weapons-grade nuclear material Chapter 18: Uranium-236 Chapter 19: Burnup Chapter 20: Liquid fluoride thorium reactor Chapter 21: Nuclear transmutation (II) Answering the public top questions about thorium fuel cycle. (III) Real world examples for the usage of thorium fuel cycle in many fields. (IV) 17 appendices to explain, briefly, 266 emerging technologies in each industry to have 360-degree full understanding of thorium fuel cycle' technologies. Who This Book Is For Professionals, undergraduate and graduate students, enthusiasts, hobbyists, and those who want to go beyond basic knowledge or information for any kind of thorium fuel cycle.

The nuclear fuel cycle is characterised by the wide range of scientific disciplines and technologies it employs. The development of ever more integrated processes across the many stages of the nuclear fuel cycle therefore confronts plant manufacturers and operators with formidable challenges. Nuclear fuel cycle science and engineering describes both the key features of the complete nuclear fuel cycle and the wealth of recent research in this important field. Part one provides an introduction to the nuclear fuel cycle. Radiological protection, security and public acceptance of nuclear technology are considered, along with the economics of nuclear power. Part two goes on to explore materials mining, enrichment, fuel element design and fabrication for the uranium and thorium nuclear fuel cycle. The impact of nuclear reactor design and operation on fuel element irradiation is the focus of part three, including water and gas-cooled reactors, along with CANDU and Generation IV designs. Finally, part four reviews spent nuclear fuel and radioactive waste management. With its distinguished editor and international team of expert contributors, Nuclear fuel cycle science and engineering provides an important review for all those involved in the design, fabrication, use and disposal of nuclear fuels as well as regulatory bodies and researchers in this field. Provides a comprehensive and holistic review of the complete nuclear fuel cycle Reviews the issues presented by the nuclear fuel cycle, including radiological protection and security, public acceptance and economic analysis Discusses issues at the front-end of the fuel cycle, including uranium and thorium mining, enrichment and fuel design and fabrication

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.

Proceedings of an International Conference organized by the British Nuclear Energy Society and co-sponsored by the Royal Society of Chemistry and the Institution of Metallurgists LONDON, 9-12 NOVEMBER 1981

A Joint Study was started in 2005 and completed in 2007 within the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). Canada, China, France, India, Japan, the Republic of Korea, the Russian Federation, and Ukraine participated in this study. The objectives were to assess a nuclear energy system based on a closed fuel cycle (CNFC) with fast reactors (FR) regarding its sustainability, determine milestones for the nuclear energy system deployment, and establish frameworks for, and areas of, collaborative R&D work. The assessment was carried out in accordance with requirements of INPRO methodology and guiding documents of the Joint Study developed and approved by the participating parties (Canada and Ukraine participated in the discussions during the Joint Study but did not contribute to the assessments themselves)