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Post-irradiation Examination Techniques for Research Reactor Fuels

Post-irradiation Examination Techniques for Research Reactor Fuels PDF Author: IAEA
Publisher: International Atomic Energy Agency
ISBN: 920102021X
Category : Technology & Engineering
Languages : en
Pages : 149

Book Description
Post-irradiation examination (PIE) is an indispensable step in the selection of new or improved research reactor fuel, and in the characterization and understanding of its in-core behaviour. This publication provides an introduction to PIE techniques. It describes a typical PIE process from intercycle inspections in the reactor pool or channel, to hot cell PIE, which is subdivided into non-destructive and destructive testing techniques with their typical output, advantages and drawbacks, and their applicability to understanding fuel irradiation behaviour. Much of the work presented in this publication originated from the research and development of new low enriched uranium research reactor fuels. Intended readers include research reactor operators, regulators and their technical support organizations, fuel developers and manufacturers, laboratory staff, and policy makers.

Post-irradiation Examination Techniques for Research Reactor Fuels

Post-irradiation Examination Techniques for Research Reactor Fuels PDF Author: IAEA
Publisher: International Atomic Energy Agency
ISBN: 920102021X
Category : Technology & Engineering
Languages : en
Pages : 149

Book Description
Post-irradiation examination (PIE) is an indispensable step in the selection of new or improved research reactor fuel, and in the characterization and understanding of its in-core behaviour. This publication provides an introduction to PIE techniques. It describes a typical PIE process from intercycle inspections in the reactor pool or channel, to hot cell PIE, which is subdivided into non-destructive and destructive testing techniques with their typical output, advantages and drawbacks, and their applicability to understanding fuel irradiation behaviour. Much of the work presented in this publication originated from the research and development of new low enriched uranium research reactor fuels. Intended readers include research reactor operators, regulators and their technical support organizations, fuel developers and manufacturers, laboratory staff, and policy makers.

Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 978

Book Description


Small Specimen Test Techniques

Small Specimen Test Techniques PDF Author: ASTM International Committee E10 on Nuclear Technology and Applications
Publisher: ASTM International
ISBN: 0803128975
Category : Light water reactors
Languages : en
Pages : 495

Book Description


Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 438

Book Description


NUREG/CR.

NUREG/CR. PDF Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 228

Book Description


Light Water Reactor Fuel Enrichment Beyond the Five Per Cent Limit: Perspectives and Challenges

Light Water Reactor Fuel Enrichment Beyond the Five Per Cent Limit: Perspectives and Challenges PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201109200
Category : Technology & Engineering
Languages : en
Pages : 56

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.

Guidebook on Destructive Examination of Water Reactor Fuel

Guidebook on Destructive Examination of Water Reactor Fuel PDF Author: International Atomic Energy Agency
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 80

Book Description
This guidebook gives a complete survey of destructive techniques available to perform microstructural examinations, elemental and isotopic analyses and measurement of physical, chemical and mechanical properties of irradiated fuel and structural materials, and describes asociated refabrication and instrumentation techniques. Non-destructive examination (NDE) data are verified by destructive examination (DE) data. The data were submitted to the IAEA by hot laboratories from 12 countries and one international organization (CEC/ITU) during the period 1992-1995. Together with IAEA Technical Reports Series No.322 (1991), Guidebook on non-destructive examination of water reactor fuel, it presents the most comprehensive summary of post-irradiation examination techniques to date.

Activation Analysis Handbook

Activation Analysis Handbook PDF Author: R Koch
Publisher: Elsevier
ISBN: 0323159656
Category : Science
Languages : en
Pages : 230

Book Description
Activation Analysis Handbook focuses on the importance of activation analysis in the examination of trace elements in materials. The book contains examples of activation analysis techniques and application of these techniques to provide solutions to problems in various scientific disciplines. Divided into four chapters, the book starts by giving an outline of the history and growth of activation analysis, including the general technique involved. The discussions proceed by taking into consideration the theoretical aspects of activation analysis, giving emphasis to basic concepts, sources of nuclear data and experimental methods, and selection of activation reactions. The book also considers the experimental methods in activation analysis. Other topics discussed are irradiation facilities; the preparation and encapsulation of samples; irradiations; and post-irradiation assays. The last part deals with the tabulation of elements and their corresponding atomic numbers; the key to tabulation; and a tabulation of nuclear data and experimental methods for activation analysis. The text is a good source of data for readers who are interested in activation analysis.

Small Specimen Test Techniques Applied to Nuclear Reactor Vessel Thermal Annealing and Plant Life Extension

Small Specimen Test Techniques Applied to Nuclear Reactor Vessel Thermal Annealing and Plant Life Extension PDF Author: W. R. Corwin
Publisher: ASTM International
ISBN: 0803118694
Category : Annealing of metals
Languages : en
Pages : 460

Book Description


Characterization and Testing of Materials for Nuclear Reactors

Characterization and Testing of Materials for Nuclear Reactors PDF Author: International Atomic Energy Agency
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 158

Book Description
Industrial growth, energy consumption are seen as measures towards economic developments. With increase in industrial development worldwide, the demand of energy is continually on the rise. Today, the energy industry is facing many challenges. Nuclear fission and nuclear fusion are seen as important future energy sources. Development of innovative reactor designs with large efficiency for fuel burn up is one of the needs of fission reactors. The materials resistant to high dose of radiations in fusion reactors is another major challenge. The production of electricity without global warming is an important pressing demand on the energy sector. The demands on quality control of components for nuclear and heavy industry are very stringent. Development of well characterized, high quality materials is therefore essential for safe, efficient and reliable operation of engineering components. The diagnosis of failure of machinery parts comes from the post operational characterization of materials. Various destructive and non-destructive techniques are used for this purpose. Research reactors have played an important role in non-destructive characterization of materials and have contributed to technology development. This publication focuses on characterization of materials for industries in general and nuclear energy sector in particular. The main focus is on research reactor based techniques with some discussion on other allied methods like positron annihilation.--Publisher's description.