Quality and Reliability Aspects in Nuclear Power Reactor Fuel Engineering PDF Download
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Author: IAEA
Publisher: International Atomic Energy Agency
ISBN: 9201500238
Category : Technology & Engineering
Languages : en
Pages : 182
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Book Description
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.
Author: IAEA
Publisher: International Atomic Energy Agency
ISBN: 9201500238
Category : Technology & Engineering
Languages : en
Pages : 182
Get Book Here
Book Description
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.
Author: IAEA.
Publisher:
ISBN: 9789201499233
Category :
Languages : en
Pages : 0
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Book Description
Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201639196
Category : Technology & Engineering
Languages : en
Pages : 180
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Book Description
This publication summarizes the findings and conclusions of an IAEA coordinated research project (CRP) on fuel modelling in accident conditions, which was initiated under the IAEA Action Plan on Nuclear Safety following the Fukushima accident. The overall aim of the project was to analyse and better understand fuel behavior in accident conditions, with a focus on loss of coolant accidents. In the course of the project the participants used a mixture of data derived from accident simulation experiments, in particular data designed to investigate the fuel behaviour during design basis accident and design extension conditions. They carried out calculations on priority cases selected from a matrix of cases identified at the first research coordination meeting and designed to support their individual priorities. These priority cases were chosen as the best available to help determine which of the many models used in the codes best reflect reality. The CRP provided an ideal platform to compare their code results with others and especially with experimental data, to which they otherwise would not have had access. The achievements made within this CRP fostered new collaborations and enhanced the development and improvement of common models and highlighted differences in the interpretation of some experiments and therefore in the use of the codes ? the so-called user effects.
Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201109200
Category : Technology & Engineering
Languages : en
Pages : 56
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Book Description
The limitation of 235U enrichment is a current concern among IAEA Member States. In response, work has been undertaken to provide a platform to facilitate a comprehensive review of the current status, prospects and challenges associated with the use of fuels having enrichments higher than 5 % 235U in light water reactors. This publication is the outcome of two technical meetings and compiles the results and conclusions in terms of benefits to be obtained from the use of high assay low enriched uranium (HALEU) fuel, with due consideration of safety issues that arise from its use. It details technological options and corresponding issues regarding fuel and core design, safety analysis and assessments relevant to manufacturing, handling, transportation, storage, irradiation, and performance in normal and accident conditions.
Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201043191
Category : Business & Economics
Languages : en
Pages : 65
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Book Description
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.
Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 140
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Book Description
Author: International Nuclear Safety Advisory Group
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 118
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Book Description
The present report is a revision of Safety Series No. 75-INSAG-3 (1988), updating the statements made on the objectives and principles of safe design and operation for electricity generating nuclear power plants. It includes the improvements made in the safety of operating nuclear power plants and identifies the principles underlying the best current safety policies to be applied in future plants. It presents INSAG's understanding of the principles underlying the best current safety policies and practices of the nuclear power industry.
Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 112
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Book Description
The Nuclear Fuel Cycle Simulation System (VISTA) is a simulation system which estimates long term nuclear fuel cycle material and service requirements as well as the material arising from the operation of nuclear fuel cycle facilities and nuclear power reactors. It is a scenario based simulation tool which can model several nuclear fuel cycle options including existing nuclear power reactor types and future possible reactor types. The past operations of the power reactors and fuel cycle facilities can be modelled in the system, in order to estimate the current amount of spent fuel stored or total Pu in stored spent fuel. It can also accept future projections for nuclear power and other scenario parameters in order to predict future fuel cycle material requirements.The model has been designed to be an optimum mixture of simplicity, speed and accuracy. It does not require too many input parameters if the purpose is just to compare the requirements for selected scenarios. Furthermore, the accuracy of the system can be improved by introducing more detailed and correct sets of input parameters.
Author: Jianqiao Liu
Publisher: Springer Nature
ISBN: 9819971578
Category : Science
Languages : en
Pages : 384
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Book Description
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
Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201092205
Category : Technology & Engineering
Languages : en
Pages : 313
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Book Description
Descriptive Uranium Deposit and Mineral System Models This publication provides a set of systematic descriptive models for each uranium deposit type, subtype and class, using a consistent approach to summarise the same types of information for each. Each model is intended to have a standalone capability, using a tabular style that is typical of conventional mineral resource industry standards. Each deposit model includes a map showing the distribution of deposits, and grade-tonnage graphs. Collectively, these databases and models form a basis for assessing the global distribution of uranium deposits and evaluating supply-demand scenarios. With these, the IAEA can provide the capability for Member States to assess the potential of remaining -- or speculative -- uranium resources for long term supply beyond identified resources in a consistent and reproducible manner.
