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Post Irradiation Examination Techniques For Research Reactor Fuels
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Book Synopsis Post-irradiation Examination Techniques for Research Reactor Fuels by : IAEA
Download or read book Post-irradiation Examination Techniques for Research Reactor Fuels written by IAEA and published by International Atomic Energy Agency. This book was released on 2023-04-18 with total page 149 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Book Synopsis Post-Irradiation Examination Techniques for Research Reactor Fuels by : International Atomic Energy Agency
Download or read book Post-Irradiation Examination Techniques for Research Reactor Fuels written by International Atomic Energy Agency and published by . This book was released on 2023-07-31 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Author :International Atomic Energy Agency Publisher :International Atomic Energy Agency ISBN 13 :9789201536235 Total Pages :0 pages Book Rating :4.5/5 (362 download)
Book Synopsis Assessment of Post-Irradiation Examination Techniques for Advanced Reactor Fuel and Materials by : International Atomic Energy Agency
Download or read book Assessment of Post-Irradiation Examination Techniques for Advanced Reactor Fuel and Materials written by International Atomic Energy Agency and published by International Atomic Energy Agency. This book was released on 2024-04-08 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication has been developed based on the results of the Technical Meeting on Advances in Post-Irradiation Examination Techniques for Power-Reactor Irradiated Fuels and Innovative Fuels held in July 2021. It explores the use of existing and new post-irradiation examination (PIE) techniques for the study of next-generation fuel types. Specifically, this publication provides an overall understanding of what important performance parameters are typically studied for each fuel type to properly assess its performance, and what are the relevant PIE techniques required for the analyses. Its intended audience comprises nuclear fuel designers, manufacturers, operators, regulators, academia and policy makers who work with the nuclear fuel community
Book Synopsis Post-irradiation Examination Techniques for Water Reactor Fuel by :
Download or read book Post-irradiation Examination Techniques for Water Reactor Fuel written by and published by . This book was released on 1991 with total page 164 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Post-irradiation Examination and In-pile Measurement Techniques for Water Reactor Fuels by :
Download or read book Post-irradiation Examination and In-pile Measurement Techniques for Water Reactor Fuels written by and published by . This book was released on 2009 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication represents a summary and proceedings of two technical meetings on the subjects of 1) hot cell post-irradiation examination (PIE) techniques and poolside inspection of water reactor fuel assemblies, and 2) fuel rod instrumentation and in-pile measurement techniques. It provides an overview of the status of in-pile and post-irradiation techniques of water reactor fuel examination with an emphasis on experimental methods applied to high burnup fuel. Further important items addressed at these meetings were the information on progress achieved in non-destructive and destructive PIE techniques used for investigation of water reactor fuels, advanced PIE techniques such as 3-D tomography, as well as advanced in-pile measurement techniques for a better understanding of mechanisms of fuel behavior under irradiation.
Book Synopsis Post-irradiation Examination Techniques for Water Reactor Fuel by :
Download or read book Post-irradiation Examination Techniques for Water Reactor Fuel written by and published by . This book was released on 1991 with total page 163 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :International Atomic Energy Agency Publisher :International Atomic Energy Agency ISBN 13 :9789201627094 Total Pages : pages Book Rating :4.6/5 (27 download)
Book Synopsis Post-irradiation Examination and In-pile Measurement Techniques for Water Reactor Fuels by : International Atomic Energy Agency
Download or read book Post-irradiation Examination and In-pile Measurement Techniques for Water Reactor Fuels written by International Atomic Energy Agency and published by International Atomic Energy Agency. This book was released on 2010-02-01 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication represents a summary and proceedings of two technical meetings on the subjects of 1) hot cell post-irradiation examination (PIE) techniques and poolside inspection of water reactor fuel assemblies, and 2) fuel rod instrumentation and in-pile measurement techniques. It provides an overview of the status of in-pile and post-irradiation techniques of water reactor fuel examination with an emphasis on experimental methods applied to high burnup fuel. Further important items addressed at these meetings were the information on progress achieved in non-destructive and destructive PIE techniques used for investigation of water reactor fuels, advanced PIE techniques such as 3-D tomography, as well as advanced in-pile measurement techniques for a better understanding of mechanisms of fuel behavior under irradiation.
Book Synopsis Post-irradiation Examination Techniques by : Penelope Cartledge
Download or read book Post-irradiation Examination Techniques written by Penelope Cartledge and published by . This book was released on 1972 with total page 264 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Advanced Post-irradiation Examination Techniques for Water Reactor Fuel by :
Download or read book Advanced Post-irradiation Examination Techniques for Water Reactor Fuel written by and published by . This book was released on 2002 with total page 222 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Light Water Reactor Fuel Enrichment Beyond the Five Per Cent Limit: Perspectives and Challenges by : International Atomic Energy Agency
Download or read book Light Water Reactor Fuel Enrichment Beyond the Five Per Cent Limit: Perspectives and Challenges written by International Atomic Energy Agency and published by . This book was released on 2020-10-12 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Book Synopsis National Postirradiation Examination Workshop Report by :
Download or read book National Postirradiation Examination Workshop Report written by and published by . This book was released on 2011 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A National Post-Irradiation-Examination (PIE) Workshop was held March 29-30, 2011, in Washington D.C., stimulated by the DOE Acting Assistant Secretary for Nuclear Energy approval on January 31, 2011 of the "Mission Need Statement for Advanced Post-Irradiation Examination Capability". As stated in the Mission Need, "A better understanding of nuclear fuels and material performance in the nuclear environment, at the nanoscale and lower, is critical to the development of innovative fuels and materials required for tomorrow's nuclear energy systems." (2011) Developing an advanced post-irradiation capability is the most important thing we can do to advance nuclear energy as an option to meeting national energy goals. Understanding the behavior of fuels and materials in a nuclear reactor irradiation environment is the limiting factor in nuclear plant safety, longevity, efficiency, and economics. The National PIE Workshop is part of fulfilling or addressing Department of Energy (DOE) missions in safe and publically acceptable nuclear energy. Several presentations were given during the opening of the workshop. Generally speaking, these presentations established that we cannot continue to rely on others in the world to provide the capabilities we need to move forward with nuclear energy technology. These presentations also generally identified the need for increased microstructural understanding of fuels and materials to be coupled with modeling and simulation, and increased accessibility and infrastructure to facilitate the interaction between national laboratories and participating organizations. The overall results of the work of the presenters and panels was distilled into four primary needs 1. Understanding material changes in the extreme nuclear environment at the nanoscale. Nanoscale studies have significant importance due to the mechanisms that cause materials to degrade, which actually occur on the nanoscale. 2. Enabling additional proficiency in experimentation and analysis through robust modeling coupled with advanced characterization. 3. Advancing the infrastructure and accessibility of physical and administrative systems needed to meet the needs of participating organizations that are subject to different time cycles and constraints that make working and collaborating the national laboratories challenging. 4. Pursuing in-situ analysis and instrumentation to support the examination of dynamic changes to materials' microstructure, deformation, and surface effects as they occur with time scales rather than the static comparison offered by current PIE methods. This Workshop Report responds to the research challenges for advanced/future PIE needs for nuclear materials development outlined by Energy Secretary Chu and the DOE-NE Research and Development Roadmap report, which was delivered to Congress in April 2010, (DOE-NE, 2010) by identifying the technial needs for fuel and material development specifically related to PIE. The information from the panels address these research challenges by identifying specific needs related to each of the topical areas. The focus of the Workshop was to identify gaps in the enabling capabilities for nuclear energy research and to identify high-priority fundamental capabilities to enable research to be completed that would likely have high impact on enabling nuclear energy as a significant contributor to energy production portfolios.
Book Synopsis The Post-irradiation Examination of a PuO2-UO2 Fast Reactor Fuel by : J. M. Gerhart
Download or read book The Post-irradiation Examination of a PuO2-UO2 Fast Reactor Fuel written by J. M. Gerhart and published by . This book was released on 1961 with total page 124 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis The Post-irradiation Examination of a PuO2-UO2 Fast Reactor Fuel by :
Download or read book The Post-irradiation Examination of a PuO2-UO2 Fast Reactor Fuel written by and published by . This book was released on 1961 with total page 119 pages. Available in PDF, EPUB and Kindle. Book excerpt: A program was carried out to determine the irradiation behavior of a PuO2-UO2 fast reactor fuel prototype. Forty stainless steel clad fuel specimens were fabricated, encapsulated, and irradiated in the General Electric Test Reactor to burnups ranging from 5000 to 99,000 MWD/T, and at heat fluxes ranging from 0.5 x 106 to 1.6 x 106 Btu/ hr-ft2. The cladding surface temperature ranged from 700 to 1200 deg F with most specimens in the 1000 to 1200 deg F range. All specimens were irradiated without rapture despite the high performance conditions imposed. Following irradiation, the fuel specimens were examined in the Radioactive Materials Laboratory. The post-irradiation examination consisted of dimensional measurements, gamma scans, determination of fission gas release, visual examination of the fuel, measurement of central voids, and metallographic examination of selected samples. Specimen and capsule fabrication is discussed, and the results of the postirradiation examination are presented and discussed.
Download or read book Post-irradiation Examination written by and published by Thomas Telford Publishing. This book was released on 1981 with total page 380 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Post-irradiation-examination of Irradiated Fuel Outside the Hot Cell by :
Download or read book Post-irradiation-examination of Irradiated Fuel Outside the Hot Cell written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Because of their high radioactivity, irradiated fuels are commonly examined in a hot cell. However, the Idaho National Laboratory (INL) has recently investigated irradiated U-Mo-Al metallic fuel from the Reduced Enrichment for Research and Test Reactors (RERTR) project using a conventional unshielded scanning electron microscope outside a hot cell. This examination was possible because of a two-step sample-preparation approach in which a small volume of fuel was isolated in a hot cell and shielding was introduced during later stages of sample preparation. The resulting sample contained numerous sample-preparation artifacts but allowed analysis of microstructures from selected areas.
Book Synopsis Nondestructive Examination of Fuel Plates for the Rertr Fuel Development Experiments by :
Download or read book Nondestructive Examination of Fuel Plates for the Rertr Fuel Development Experiments written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear fuel is the core component of reactors that is used to produce the neutron flux required for irradiation research purposes as well as commercial power generation. The development of nuclear fuels with low enrichments of uranium is a major endeavor of the RERTR program. In the development of these fuels, the RERTR program uses nondestructive examination (NDE) techniques for the purpose of determining the properties of nuclear fuel plate experiments without imparting damage or altering the fuel specimens before they are irradiated in a reactor. The vast range of properties and information about the fuel plates that can be characterized using NDE makes them highly useful for quality assurance and for analyses used in modeling the behavior of the fuel while undergoing irradiation. NDE is also particularly useful for creating a control group for post-irradiation examination comparison. The two major categories of NDE discussed in this paper are X-ray radiography and ultrasonic testing (UT) inspection/evaluation. The radiographic scans are used for the characterization of fuel meat density and homogeneity as well as the determination of fuel location within the cladding. The UT scans are able to characterize indications such as voids, delaminations, inclusions, and other abnormalities in the fuel plates which are generally referred to as debonds as well as to determine the thickness of the cladding using ultrasonic acoustic microscopy methods. Additionally, the UT techniques are now also being applied to in-canal interim examination of fuel experiments undergoing irradiation and the mapping of the fuel plate surface profile to determine fuel swelling. The methods used to carry out these NDE techniques, as well as how they operate and function, are described along with a description of which properties are characterized.
Book Synopsis Research Reactor Spent Fuel Management: Options and Support to Decision Making by : IAEA
Download or read book Research Reactor Spent Fuel Management: Options and Support to Decision Making written by IAEA and published by International Atomic Energy Agency. This book was released on 2021-12-14 with total page 147 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication, resulting from an IAEA coordinated research project (CRP), provides information about available strategies for research reactor spent fuel management, and presents a decision methodology to assist those selecting among several options, to identify the preferred approach for their specific situation. The decision support tools were developed to consider not only the cost of the possible research reactor spent fuel management strategies, but also the non-economic factors that might influence their selection. Examples of the technologies that are currently used by some IAEA Member States are provided. Additionally, this publication provides information about the Excel based decision-support tools developed as part of this CRP, along with case studies and tutorials to assist users.
