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Presents the material properties of all unirradiated Uranium-Molybdenum (U-Mo) fuel constituents that are essential for fuel designers and reactor operators to evaluate the fuel's performance and safety for research 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.
Reviews the current state of technology regarding combustible gas related safety issues in water cooled nuclear reactors, with a specific focus on post-Fukushima Daiichi accident developments. The recent results obtained from experimental and analytical research on hydrogen/combustible gas behaviour are discussed.
Analyses and provides new insights into the different approaches followed by the nuclear industry for the effective management of nuclear facilities, as well as guidance to develop a comprehensive requirement management programme in nuclear facilities.
Provides an introduction to gamma computed tomography for non-destructive evaluation imaging in the simplest configuration. The guide is intended to be of use to the non-destructive testing community, currently practicing conventional radiography techniques.
Focuses on the engineering judgement necessary to apply each of the design requirements in SSR-2/1 (Rev. 1), and also the entire set of requirements, to light water cooled and high temperature gas cooled SMRs.
Provides a summary of the operating experience feedback from the events reported to the Fuel Incident Notification and Analysis System since it was launched in 1992. The publication has a focus on the root causes, lessons identified, and corrective actions taken to prevent the occurrence of similar events.
Provides current information on considerations about environmental impact assessments (EIAs) related to small modular reactors. Under many regulatory regimes, the EIA report is a prerequisite for licensing and an important tool to confirm that the potential site is suitable for the future construction and operation of a reactor.
Presents a collection of current practices of fuel acceptance criteria used in States with operating pressurized heavy water reactors (PHWRs) and provides the technical justification available for such criteria conditions.
New geochemical and mineralogical data from research conducted under an IAEA coordinated research project has resulted in a better understanding of the genesis of uranium and thorium mineralization. This publication presents a summary of the research and selected papers from the project's partners.
Describes several available techniques with sealed radioactive sources, by showing examples of their use in industrial applications and by demonstrating how they can be used to improve process efficiency and to save money. The focus is on two major techniques with sealed radioactive sources: gamma scanning and neutron backscattering.
Focuses on ways to improve crop productivity and sustainability through water and salinity management and defines approaches and technologies to assess and monitor soil water content and salinity. The test results of a new landscape soil moisture measuring tool (cosmic ray neutron sensor) for area-wide soil water measurements are also presented.
Presents a set of examples of different approaches for estimating potential exposures in different countries based on participants' experience and considering the IAEA Safety Standard on a generic framework for consideration of radiological environmental impact, including potential exposures.
Provides guidance and recommendations to nuclear organizations by offering a practical approach to assessing the behavioural competencies for safe, secure and effective performance across the nuclear workforce. The book outlines a variety of tools and approaches that can aid behavioural assessment processes.
Presents the outcome of an IAEA coordinated research project titled Pathways to Energy from Inertial Fusion
Evaluates the different coolant options considered for nuclear applications with a fast neutron spectrum, compiles the latest information in the field and identifies research needs. In this study, systems cooled by light and heavy liquid metals, molten salts, as well as gas and water choices are analysed and discussed.
This publication is the result of an IAEA technical meeting and reports on Member States' capabilities in modelling, predicting and improving their understanding of the behaviour of nuclear fuel under accident conditions. The main results and outcomes of a coordinated research project (CRP) on this topic are also presented.
Describes the general concept of using quantitative and qualitative information to be integrated in making safety related decisions. The publication also provides practical insights on the selection of the various factors that could be included in the integrated risk informed decision making process.
Provides a description of the Rossendorf coolant mixing test facility, used to provide benchmark experiments related to the phenomena of pressurized thermal shock and boron dilution, the calculation results using computational fluid dynamics (CFD) methods, and the conclusions drawn from comparison of CFD results with experimental measurements.
Draws on the work carried out during an IAEA coordinated research project to benchmark computational fluid dynamics (CFD) codes used in fuel assembly design and model options and methods against 'CFD quality' experimental data under single phase flow conditions.
Explains the concepts of quality assurance and quality control. The publication provides examples, illustrated by good practices, of their implementation within the processes of the management systems of nuclear facilities and describes how they are managed through interfaces with suppliers and subcontractors.
This publication results from a technical meeting on phenomenology and technologies relevant to in-vessel melt retention (IVMR) and ex-vessel corium cooling (EVCC). The purpose is to capture the state of knowledge related to phenomenology and technologies as well as the challenges and issues relevant to IVMR and EVCC for water cooled reactors.
Examines the technical basis for the use of seismic isolation systems in nuclear installations. There are many benefits of seismic isolation in design and construction of new facilities and in the retrofitting of existing nuclear installations.
Describes and summarizes the work of the MODARIA (modelling and data for radiological impact assessments) Programme Working Group 6. MODARIA was set up to continue the IAEA's activities in testing, comparing and developing guidance on the application of models to assess radiation exposures to humans and the environment.
Provides guidance for assessing the sustainability of a nuclear energy system (NES) in the area of nuclear fuel cycle facility (NFCF) safety. The publication deals with NFCFs that may be involved in the NES, such as mining, milling, refining, conversion, enrichment, fuel fabrication, spent fuel storage, and spent fuel reprocessing facilities.
Presents information about existing practices in regulatory bodies for managing regulatory experience and, through a series of experts' meetings an assessment of that information is presented to identify possible measures that might help regulatory bodies enhance their current practices where necessary.
Contractor personnel provide essential services to nuclear power plants (NPPs). They have required levels of competency and must interface effectively with nuclear power plant personnel when performing their assigned duties. It is in this context that this publication offers a framework for assuring the competence of such contractor personnel.
Providing guidance to those assessing a planned nuclear energy system (or a nuclear reactor), this publication provides detail on how to apply the INPRO methodology for sustainability assessment in the area of safety of nuclear reactors. It augments the information presented in the earlier INPRO publications.
Presents the latest update to the INPRO methodology for Nuclear Energy Systems sustainability assessment in the area of waste management, and reflects detailed discussions held at an IAEA technical meeting.
Illustrates the state of the art in supercritical water cooled reactor (SCWR) research and development. This is a key supporting publication to researchers and engineers pursuing the development of SCWRs or equipment/components operating at supercritical pressures.
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