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The purpose of this report is to provide a combined presentation of the worldwide experience gained on fuel failures in water cooled reactors and to give statistical data on fuel failures for the period 1987 to 1994. It contains detailed descriptions of primary and secondary failure mechanisms which occurred in 'western' type boiling and pressurized water reactors (BWRs and PWRs), Soviet type pressurized light water reactors (WWERs) and Canadian type heavy water reactors (CANDUs). It also includes information on detection, examination and analysis of fuel failures as well as on fuel failure prevention and management in plant operation.
Presents worldwide statistics on fuel failure rates, covering about 96% of water cooled reactor fuels. The publication also describes modern methods of detection and examination of fuel failures, analyses their mechanisms and root causes, and recommends failure prevention and mitigation measures.
Since the 1970s, the IAEA has been involved in the analysis of fuel failures in water cooled reactors in normal (non-accident) operational conditions. This updated version of IAEA Nuclear Energy Series No. NF-T-2.1 provides information on all aspects of fuel failures in current nuclear power plant operations.
The Water Reactor Fuel Performance Meeting (WRFPM) held in Asia has merged with TopFuel in Europe and LWR Fuel Performance in the United States to form the globally most influential conference in the field of nuclear fuel research. WRFPM2023 is organized by Chinese Nuclear Society (CNS) in cooperation with the Atomic Energy Society of Japan (AESJ), Korean Nuclear Society (KNS), European Nuclear Society (ENS), American Nuclear Society (ANS), the Interna-tional Atomic Energy Agency (IAEA) with the support from China Nuclear Energy In¬dustry Corporation (CNEIC) and TVEL. Conference Topics: 1. Advances in water reactor fuel technology and testing 2. Operation and experience 3. Transient and off-normal fuel behaviour and safety related issues 4. Fuel cycle, used fuel storage and transportation 5. Innovative fuel and related issues 6. Fuel modelling, analysis and methodology
This updated version of Nuclear Energy Series NF-T-2.1 provides information on all aspects of fuel failures in current nuclear power plant operations.
Pressurized Heavy Water Reactors: CANDU, the seventh volume in the JSME Series on Thermal and Nuclear Power Generation series, provides a comprehensive and complete review of a single type of reactor in a very accessible and practical way. The book presents the full lifecycle, from design and manufacturing to operation and maintenance, also covering fitness-for-service and long-term operation. It does not relate to any specific vendor-based technology, but rather provides a broad overview of the latest technologies from a variety of active locations which will be of great value to countries invested in developing their own nuclear programs. Including contemporary capabilities and challenges of nuclear technology, the book offers practical solutions to common problems faced, along with the safe and approved processes to reach suitable solutions. Professionals involved in nuclear power plant lifecycle assessment and researchers interested in the development and improvement of nuclear energy technologies will gain a deep understanding of PHWR nuclear reactor physics, chemistry and thermal-hydraulic properties. - Provides a complete reference dedicated to the latest research on Pressurized Heavy Water Reactors and their economic and environmental benefits - Goes beyond CANDU reactors to analyze the popular German and Indian designs, as well as plant design in Korea, Romania, China and Argentina - Spans all phases of the nuclear power plant lifecycle, from design, manufacturing, operation, maintenance and long-term operation
Improved fuel reliability means reduced fuel failures in reactor operation. Fuel failures, with their consequent adverse impact on the environment and requirements for additional waste management, result in costs for remediation, 'failed core' operation and maintenance. Therefore, poor performance of fuel can lead to uncompetitive operational conditions for a nuclear power plant. A revision of the earlier edition, this publication has been significantly extended to support nuclear fuel designers, manufacturers, reactor operators, and fuel engineers and managers on fuel design and design changes, fuel manufacturing, qualification, in-reactor operation, and on-site services to achieve excellence in fuel reliability and performance and safe operation of nuclear fuel under all applicable plant states.
Boiling Water Reactors, Volume Four in the JSME Series on Thermal and Nuclear Power Generation compiles the latest research in this very comprehensive reference that begins with an analysis of the history of BWR development and then moves through BWR plant design and innovations. The reader is guided through considerations for all BWR plant features and systems, including reactor internals, safety systems and plant instrumentation and control. Thermal-hydraulic aspects within a BWR core are analyzed alongside fuel analysis before comparisons of the latest BWR plant life management and maintenance technologies to promote safety and radiation protection practices are covered. The book's authors combine their in-depth knowledge and depth of experience in the field to analyze innovations and Next Generation BWRs, considering prospects for a variety of different BWRs, such as High-Conversion-BWRs, TRU-Burner Reactors and Economic Simplified BWRs. - Written by experts from the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers - Includes real examples and case studies from Japan, the US and Europe to provide a deeper learning opportunity with practical benefits - Considers societal impacts and sustainability concerns and goals throughout the discussion - Explores BWR plant design, thermal-hydraulic aspects, the reactor core and plant life management and maintenance in one complete resource