Search results for ""Author IAEA""

The IAEA organizes International Collaborative Standard Problems (ICSPs) to facilitate co-operation on advancing reactor technology related activities. These activities include the development, assessment and validation of computer codes for design and safety analysis of nuclear power plants. The objective of this ICSP was to develop and facilitate open access to a set of standardized numerical test problems for selected postulated transients in pressurized heavy water reactors (PHWRs). These manufactured test problems are different from typical benchmark problems in that the specification is designed for a stylized model of a generic CANDU-6 PHWR and a reference solution is not postulated. The set of standardized numerical test problems supports the development of simulation codes, methods, and coupling frameworks. This publication provides a description of four numerical test problems, the participants' individual multi-physics methodologies applied, and simulations carried out, an independent synthesis of the results, and the lessons learned from the exercise.

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There is renewed interest in Member States in the development and deployment of small modular reactors (SMRs). Specific technical characteristics of this reactor type introduce new deployment possibilities. This publication provides current information on considerations about environmental impact assessments (EIAs) related to SMRs. 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. Therefore, this publication which discusses approaches to address specific issues related to the EIA for SMRs will be of use to technology holders and licensing authorities.

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Quality assurance is a crucial part of all aspects of nuclear medicine practice. The objective of this publication is to provide professionals in nuclear medicine centres with detailed quality control test procedures for the scintillation camera and computer system. Three types of quality tests are described in detail: acceptance, reference and routine tests for the scintillation camera, both in single and multiple head configurations, for obtaining images and quantitative data in planar imaging mode; whole body imaging mode; and single-photon emission computed tomography (SPECT). The publication is primarily intended to be of use to medical physicists, technologists and other healthcare professionals who are responsible for ensuring optimal performance of imaging instruments, particularly SPECT systems. It may also be useful to managers, clinicians and other decision makers who are responsible for implementing quality assurance and quality control programmes in nuclear medicine centres.

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Hazards associated with human induced external events (HIEEs) need to be considered in the evaluation of sites for nuclear installations, in the design of new nuclear installations and in the operation of existing nuclear installations. This Safety Guide provides recommendations on the evaluation of these hazards in order to meet the requirements set out in IAEA Safety Standards Series No. SSR-1, Site Evaluation for Nuclear Installations. It provides a process for identification of source of HIEEs, screening of hazards using distance and probability, and detailed evaluation to establish hazard and load characterization parameters. This publication is intended for use by organizations involved in the identification, screening, analysis, evaluation and review of hazards associated with HIEEs, and the provision of technical support, as well as regulatory bodies.

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Reporting on the results from an IAEA coordinated research project, this publication provides information on reliability data for research reactors. In addition to component reliability data, the publication provides useful information related to the preparation and application of data relevant to initiating events, human reliability, and common cause failures. It also provides guidance on the use and application of the reliability data for research reactors probabilistic safety assessments as a complementary tool to deterministic methods. This publication should be used in conjunction with the relevant IAEA Safety Standards.

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The design, operation, safety and decommissioning of research reactors involves complex processes that can be understood and improved through numerical analysis and benchmarking. This publication provides the final consolidated results of an IAEA coordinated research project (CRP). It comprises the benchmark studies, details of the calculations in the annexes and individual reports of the CRP participants in the on-line supplementary files. This publication is intended for operating organizations, researchers, regulatory bodies, reactor designers, technical support organizations and other parties interested in benchmarking the computer codes and models they use for research reactor operation and safety analysis.

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A number of IAEA Member States generate relatively small quantities of radioactive waste and/or disused sealed sources in research or in the application of nuclear techniques in medicine and industry. This publication presents a modular approach to the design of waste processing and storage facilities to address the needs of such Member States with a cost effective and flexible solution that allows easy adjustment to changing needs in terms of capacity and variety of waste streams. The key feature of the publication is the provision of practical guidance to enable the users to determine their waste processing and storage requirements, specify those requirements to allow the procurement of the appropriate processing and storage modules and install and eventually operate those modules.

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Artificial sources of radiation are commonly used in the manufacturing and service industries, research institutions and universities, and the nuclear power industry. As a result, workers can be exposed to artificial sources of radiation. There are also a significant number of workers, such as underground miners and aircrew, who are exposed to naturally occurring sources of radiation. This publication, prepared in collaboration with the International Labour Organization, and with reference to IAEA Safety Standards Series No. GSR Part 3 provides guidance for individuals and organizations on the assessment of prospective cancer risks due to occupational exposure to ionizing radiation for prevention purposes. It describes cancer risk assessment theory, models and methodologies, and offers practical examples of carrying out these assessments.

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This publication draws on data and results collated during an IAEA coordinated research project (CRP) on optimizing soil, water and nutrient use efficiency in integrated cropping-livestock production systems. The main objective of the project was to enhance food security, improve soil fertility, and mitigate greenhouse gases from agriculture using integrated cropping-livestock systems in changing climate conditions. In addition, the CRP participants developed a package of technology for farmers to increase crop production and improve their livelihoods using nuclear and related techniques.

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This Safety Guide provides recommendations on meeting the requirements of IAEA Safety Standards Series No. SSR-2/1 (Rev. 1) relevant to reactor containment and associated systems. The publication addresses the containment structure and the systems with the functions of isolation, control and management of mass and energy releases, control and limitation of radioactive releases, and control and management of combustible gases. The Safety Guide is intended for use primarily for land based, stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat generating applications, such as for district heating or desalination.

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Despite significant progress having been achieved in recent years, much remains to be done in terms of addressing the legacies from the early development of nuclear energy, including the dismantling of redundant research and fuel cycle facilities, research reactors and power plants, and the remediation of sites affected by past uranium mining and processing operations. Some countries are moving forward with dealing with these legacies, and accordingly have built up appropriate technical resources and expertise, but many national programmes still face very significant challenges. This publication discusses the barriers that prevent the implementation of decommissioning and environmental remediation (D&ER) projects and provides potential solutions to overcome the identified barriers and thereby facilitates a better implementation of D&ER programmes.

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Seismic isolation technology has the potential to significantly reduce the overall risk posed by earthquake ground motions to nuclear power plants. A testing programme is an integral part of a seismic isolation project. Not only must the isolating devices be characterized for design purposes, but also validation of the analytical procedures used in design is required. Hybrid simulation is a testing technique which is a good candidate to experimentally assess the behaviour of an isolation system. The method combines the computation of the response of the isolated structure with the experimental determination of the behaviour of full-scale isolators under the demand imposed by the movement of ground and structure. This publication contributes to the assessment of the method as a tool for the design and safety demonstration of base-isolated nuclear facility buildings.

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Within the overall objective to support the development of fast reactor technology and to extend the predictive capabilities of existing simulation tools for design and safety analysis, this publication aims to improve the understanding of key phenomena involving radioactive material transport and reduce uncertainties in the estimation of potential releases to the environment. It arises from an IAEA coordinated research project (CRP), launched to perform modelling and simulation of the source term for sodium cooled fast reactors under hypothetical severe accident conditions. The publication presents the results and conclusions of the CRP to verify and validate modelling the in-vessel and in-containment source terms. The technical aspects addressed by the CRP are divided into three main parts: the in-vessel source term estimation, the primary system/containment interface source term estimation and the in-containment phenomenology. This publication documents the models, simulations, results and discussions.

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Nuclear educational networks have demonstrated their value to support Member States in establishing, running and maintaining nuclear education programmes that are sustainable and aligned with the actual needs and priorities of the sector. Through co-operation among universities, training organizations and industry, national and international networks have enabled the retention, expansion and enhancement of nuclear educational programmes. This publication provides the background, context and drivers for developing and promoting collaboration in nuclear educational, capturing best practices and mechanisms that can aid the establishment and operation of networks. It showcases the experience and achievements of existing networks, providing practical examples of their benefits, outcomes and lessons learned. The publication will be useful to institutions seeking to develop or improve their nuclear education programmes by embarking on collaborative efforts.

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Security management for radioactive material in use, storage and associated facilities includes the establishment and implementation of policies, plans, procedures and processes for the security of radioactive material. Security management assists to ensure that the security systems are effective, reliably operated and maintained with the necessary resources. Based on extensive input from technical and legal experts, this publication sets forth security management as an essential tool to verify that personnel, procedures and equipment operate interdependently and in an integrated manner, and that the leadership and personnel responsible for security demonstrate the highest commitment towards promoting a robust nuclear security culture within the organization. This Technical Guidance references and takes into account other IAEA Nuclear Security Series publications that provide guidance relating to security management. The document further provides guidance , including on the development of a security plan for radioactive material in use and in storage and for associated facilities. The Security Plan is an essential component of an operators licensing submission package. This Technical Guidance takes into account other IAEA Nuclear Security Series publications that provide guidance relating to security management and relating to security plans.

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This publication provides guidance to States on the development, implementation, maintenance and sustainment of a national framework for managing the response to nuclear security events. Such a framework involves a structure and a set of principles and agreements around which a State can frame its nuclear security response functions, addressing the interfaces which need to exist between responding agencies to ensure effective, coordinated response. By using this Implementing Guide, a State will ensure that it has considered all relevant key issues as it develops its national framework for responding to nuclear security events.

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This publication is part of a series that aims to inform nuclear facility designers, vendors, operators and State governments about IAEA safeguards, and demonstrates how associated requirements can be considered early in the design phase of a new nuclear facility. This particular publication is applicable to the design and construction of commercial uranium enrichment plants. Safeguards by design dialogue undertaken early in the design and construction of enrichments plants facilitates the implementation of safeguards throughout all the lifecycle stages of the facility. The potential to reduce costs, avoid retrofits and achieve efficiencies both for the operator and for IAEA Member States are important drivers for the early consideration of safeguards in a nuclear facility design project.

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This publication provides technical and scientific information regarding the radiation monitoring, radio-ecological research and management of the Chernobyl Nuclear Power Plant (ChNPP) cooling pond. It focuses on the assessment of the environmental and radiological conditions after the pond drawdown, as a basis for justification of the decommissioning and remediation strategy for the pond. Special attention is paid to the analyses of remedial actions to reduce ongoing or potential doses to members of the public and staff of the ChNPP due to radiological impacts resulting from the drawdown of water level in the pond. The publication also outlines practical experience gained throughout the cooling pond decommissioning project, which started in 2014 and continues until the present. It presents data from a monitoring programme, comparing modelling predictions of the dynamics of the cooling pond drainage and related radiological and ecological impacts, with the consequences of the drawdown of the water level in the cooling pond that were actually observed. Additionally, the publication summarizes lessons learned and addresses outstanding issues.

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This publication provides a holistic approach to evaluate progress in the development of the nuclear power infrastructure based on the guidance contained in the IAEA Nuclear Energy Series No. NG-G-3.1, Milestones in the Development of a National Infrastructure for Nuclear Power. It can be used by a Member State itself, wishing to evaluate its progress (self-evaluation), or as a basis for an integrated nuclear infrastructure review (INIR) mission. This revised version combines in one publication an explanation of the methodology and the evaluation tables, takes into account all new material and lessons learned from the Fukushima Daiichi accident, and presents the results of the INIR missions implemented between 2009 and 2014.

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In industrial processes, it is useful to have a range of non-intrusive techniques that can effectively 'look' through vessel and pipe walls to measure process parameters and to identify plant problems. Sealed radioactive sources, specifically those that emit gamma radiation and neutron particles, are ideally suited for these purposes and have been used for industrial applications for many years. This publication 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 of the publication corresponds to two major techniques with sealed radioactive sources: gamma scanning and neutron backscattering, which are largely applied for diagnosis and troubleshooting in processing vessels, columns and in pipes.

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This publication describes differences in post-accident situations compared with normal decommissioning (i.e. decommissioning after a planned final shutdown) and identifies significant decision factors as applicable. It focuses on the on-site decommissioning aspects of a technical nature, which need to be addressed after a nuclear accident. Non-technical issues, such as policy and strategy, project planning, organization and management are also covered. The collection of experience on approaches, techniques, practices and implementation considerations is based on practical examples and lessons learned from past events, including the Fukushima Daiichi accident. Although the publication addresses decommissioning of nuclear power reactors after an accident, many aspects and considerations are also relevant for non-power nuclear facilities as well as legacy nuclear facilities.

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This publication focuses on the storage of spent nuclear fuel from power reactors, which is a topic of increasing importance to Member States. To support their needs, the IAEA has carried out successive coordinated research projects (CRPs) on spent fuel performance and the behaviour of spent fuel assemblies in storage since the 1980s. The findings of these CRPs have been reported in a series of publications over the past 30 years. The current publication consolidates these findings and compiles all relevant information in one referenceable source. The technical information provided in this publication will be particularly useful for experts engaged in safety assessments.

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This publication presents the proceedings of a workshop on the remediation of radioactive contamination in agriculture. The workshop brought together specialists from different countries and technical backgrounds and sought to disseminate research findings and encourage future studies aimed at the development of technologies to support sustainable agricultural production and rural development after a nuclear accident. The presentations and discussions at the meeting focused on both laboratory findings and practical field-work experience in planning and implementing remediation activities. The participants provided information related to agricultural production in Japan after the Fukushima Daiichi accident and in the many different countries affected by the Chernobyl accident. The workshop contributed to the dissemination of information and knowledge in this very distinct area and produced conclusions, recommendations and observations to enhance preparedness and response planning for nuclear emergencies and radiological incidents in relation to food and agriculture. This publication is targeted at authorities responsible for food and agriculture, international organizations working in this area, as well as professionals and academics involved in the remediation of radioactive contamination. It will also be of interest to nuclear safety or emergency planning and response specialist.

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Nuclear energy and renewables are the two principal options for low carbon energy generation. However, synergies among these resources have yet to be fully exploited, and the advantages of directly integrating these generation options are being explored. Nuclear-renewable hybrid energy systems consider opportunities to couple these energy generation sources to leverage the benefits of each technology to provide reliable, sustainable electricity to the grid and to provide low carbon energy to other energy use sectors. This publication describes the potential use of nuclear and renewable generation in coordinated, and in some cases tightly coupled, configurations to support various applications beyond electricity production, including desalination, hydrogen production and district heating. Where available, case studies are presented to describe relevant market conditions and trends, and considerations for implementation are outlined, including gaps that require additional technology and regulatory developments.

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National nuclear institutes (NNIs) contribute significantly to national development, providing services focused on developing and applying relevant technologies for the public good. While many NNIs provide commercial services and products that generate revenue, some are financially dependent on subsidies from national governments. This publication presents the outcome of a workshop which addressed the challenges for Member States regarding self-reliance and sustainability of their NNIs. Participants discussed efforts and best practices to cope with these challenges. The publication includes positive examples of tools or measures to be used in practical projects and programmes for achieving management goals towards self-reliance and sustainability. Examples of governmental policies in support of self-reliance and sustainability of NNIs are also presented. Finally, the country presentations in this publication show some examples of how NNIs cooperate with public or private stakeholders, providing some insights on how partnership opportunities can be explored.

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Safety, reliability, and productivity in the nuclear industry result from a systematic consideration of human performance. A plant or other facility consists of both the engineered system and the human users of that system. It is therefore crucial that engineering activities consider the humans who will be interacting with those systems. Engineering design, specifically instrumentation and control (I&C) design, can influence human performance by driving how plant personnel carry out work and respond to events within a nuclear power plant. As a result, human–system interfaces (HSIs) for plant operators as well as the maintenance and testing of the I&C system cannot be designed by isolated disciplines. The focus of this publication is to integrate knowledge from the disciplines of human factors engineering (HFE) and I&C to emphasize an interdisciplinary approach for the design of better HSIs and consequently improved human performance in nuclear power plants. This is accomplished by practical explanations of the HFE processes and corresponding outputs that inform the I&C development. More specifically, the publication addresses issues in the design process where collaboration between HFE, I&C and other important disciplines and stakeholders is paramount and identifies key tools and tasks for exchanging inputs and outputs between different design disciplines, particularly I&C and HFE. The practical information provided in this publication is intended to support Member States' capabilities to improve their approach to I&C through the consideration of HFE.

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The use of radiopharmaceuticals is an important tool not only for management of diseases and dysfunctions, but also for better understanding human diseases and developing effective treatment options, such as in the case of neurology. In this context, there is concern of continuous, impressive progress in nuclear medicine which is linked to the development of new radiopharmaceuticals and efficient production of relevant radioisotopes. These proceedings highlight the main findings and developments discussed during the International Symposium on Trends in Radiopharmaceuticals. They cover the key issues and advances in the field of radiopharmaceuticals from development, production, and use of diagnostic, therapeutic, and theranostic radioisotopes and radiopharmaceuticals, as well as regulatory and licensing issues related to their production. Additional topics addressed were education, certification and training methodologies. A supplementary file contains the detailed programme of the symposium and the abstracts of all oral and poster presentations.

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A plant information model (PIM) is a set of interlinked information about plant structures, systems and components, incorporating plant data, relationships and rules used to integrate, represent, and describe nuclear facility processes and data, for each phase of the facility lifecycle. Application of the PIM provides an opportunity to radically improve knowledge, information and data capture, integration, use and transfer between stakeholders if industry-wide standards and best practices are adopted. A knowledge-centric plant information model could be developed and leveraged as a modern and efficient approach to better support, manage and enable seamless sharing, transfer and use of sustainable design knowledge within and across each nuclear power plant life cycle phase. The purpose of this publication is to provide an overview of PIMs, emphasize the importance of their application in support and management of design knowledge throughout the nuclear power plant life cycle and present an overview of a knowledge-centric plant information model that builds on the basic concept of a PIM. The target users of this publication are decision-making organizations in Member States having experience with nuclear power programmes and those embarking on new nuclear power programmes.

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This publication gives practical information and examples on safety analysis principles and methods as well as the contents of licensing documentation needed to support application of IAEA safety standards to nuclear fuel cycle facilities. A systematic methodology is presented, covering the establishment of acceptance criteria, hazard evaluation, identification of postulated initiating events, analysis of accident sequences and consequences. Information is also provided on application of the results of the safety analysis in the design and operational phases, and on appropriate management system processes. The publication applies to all lifetime stages of relevant facilities and for modifications and upgrades. The information presented may be used for periodic safety reviews and consideration of extended lifetime of facilities. With respect to licensing documentation, the publication provides indicative contents and format of the safety analysis report as a higher level document that incorporates the information required at various steps in the licensing and re-licensing process.

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Cyclotrons are currently used for the preparation of a wide variety of radionuclides that have applications in single photon emission computed tomography (SPECT) and positron emission tomography (PET). Consequently, there is high demand from IAEA Member States for support in the area of radiopharmaceutical production using cyclotron produced radioisotopes. This publication describes the potential radionuclide production routes using cyclotrons in different energy ranges and provides methods for the development of targets and provides details of the chemistry for the separation of radionuclides from target materials. The readership of this publication includes scientists, operators interested in putting this technology into practice, technologists already working with cyclotrons who wish to enhance the utility of existing machines, and managers in the process of setting up radionuclide facilities in their countries. Students working towards higher level degrees in related fields may also benefit from this publication.

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This publication is a revision and combination of two Safety Guides, IAEA Safety Standards Series No. NS-G-1.1 and No. NS-G-1.3. The revision takes into account developments in instrumentation and control (I&C) systems since the publication of the earlier Safety Guides. The main changes relate to the continuing development of computer applications and the evolution of the methods necessary for their safe, secure and practical use. In addition, account is taken of developments in human factors engineering and the need for computer security. This Safety Guide also references and takes into account other IAEA safety standards and IAEA Nuclear Security Series publications that provide guidance relating to I&C design.

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This Safety Guide provides recommendations on specific safety measures to meet the requirements of IAEA Safety Standards Series No. GSR Part 3 and other relevant Safety Requirements publications on the use of X ray generators and other types of radiation sources that are used for inspection purposes and for non-medical human imaging. The recommendations provided are primarily for organisations that are authorized to use X ray generators and other types of radiation sources for such purposes, as well as for radiation protection experts, radiation protection officers and staff of regulatory bodies. The publication may also be of interest to designers and manufacturers of relevant X ray generators and sources.

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These proceedings detail how the TC programme has contributed to the establishment of national nuclear infrastructure and capabilities in Member States over six decades, in support of their national development priorities. The publication also presents examples of successful partnerships and looks to the future regarding appropriate approaches and concrete measures that will help countries to maximize their use of nuclear science and technology in achieving their development goals, including sustainable development goal targets. Key thematic areas covered include the application of nuclear science and technology in human health and nutrition, food and agriculture, water and the environment, radiation technology, energy and safety. Common issues relating to regional collaboration and networking are presented, as is the IAEA and Member States' approach to building lasting and mutually beneficial partnerships.

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As well as the application to food irradiation, nuclear techniques can be used in the detection of contaminants and the verification of the origins and authenticity of food. This publication presents the findings of a joint FAO/IAEA coordinated research project (CRP) on utilizing isotope and trace element analysis, and other complementary analytical techniques, to characterize the origin of authentic milk and dairy products sampled by the participating institutes. The purpose of the CRP was to develop a methodology to implement a sustainable system for the independent verification of the claimed origin of food. Questions concerning origin are among the first to be asked when a food safety incident arises. The results of the project described in this publication will assist Member States to better communicate the qualities and origin related attributes, or terroir, of different food commodities. In addition, verifying the origin of food can help to prevent fraud and thereby reduce barriers to trade and protect and promote added-value products with a strong regional or national identity.

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Most research reactors share the common characteristics of a long operating lifetime. With the advancement of digital technology, substantial improvements have occurred in the tools that can be applied in the maintenance and monitoring of structures, systems and components (SSCs), enabling an understanding of equipment performance far beyond that available only a few decades ago. Several of these tools, as well as the supporting technology, have been endorsed by regulatory authorities, providing further value to their application to increase availability and reliability of research reactors. These issues and related advancements were the topic of an IAEA coordinated research project and the results are presented in this publication. It provides methods and guidance for monitoring the health of rotating equipment of research reactors to avoid lengthy and costly shutdowns while promoting safe and reliable operation.

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This publication is the outcome of an IAEA coordinated research project which addressed the problem of advancing salinity in irrigated soils of arid and semi-arid regions. Seven participating countries presented their studies focusing on alternative strategies and on integrated soil and water management practices. The publication informs readers 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.

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This new revision provides guidance to States and their competent authorities on how to establish or improve, implement, maintain and sustain the elements of the nuclear security regime related to radioactive material, associated facilities and activities, with particular emphasis on the development of regulatory requirements. The publication applies to the security of radioactive material in use or in storage as well as associated facilities and associated activities and assists Member States in their regimes against unauthorized removal of the radioactive material or sabotage performed with the intent to cause harmful radiological consequences.

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The development and implementation of an appropriate infrastructure to support the successful introduction of nuclear power and its safe, secure, peaceful and sustainable application is an issue of central concern, especially for countries that are considering and planning their first nuclear power plant. In preparing the necessary nuclear infrastructure, there are several activities that need to be completed. These activities can be split into three progressive phases of development. This publication provides a description of the conditions expected to be achieved by the end of each phase to assist with the best use of resources. ‘Milestones’ refer to the conditions necessary to demonstrate that the phase has been successfully completed.

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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.

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This publication 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. Many significant advances in the understanding and development of low enriched uranium U–Mo fuels have been made since 2004, stimulated by the need to understand irradiation behavior and early fuel failures during testing. The publication presents a comprehensive overview of mechanical and physical property data from U-Mo fuel research.

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New geochemical and mineralogical data from research conducted under the IAEA coordinated research project entitled Geochemical and Mineralogical Characterization of Uranium and Thorium Deposits 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. The results are expected to enhance exploration programmes, resource evaluation and sustainable supply of uranium and thorium for peaceful purposes.

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Over the last decades, the rapid technological development of diagnostic and interventional radiology and nuclear medicine has made them major tools of modern medicine. However, at the same time the involved risks, the growing number of procedures and the increasing complexity of the procedures require competent professional staff to ensure safe and effective patient diagnosis, treatment and management. Medical physicists (or clinically qualified medical physicists) have been recognized as vital health professionals with important and clear responsibilities related to quality and safety of applications of ionizing radiation in medicine. This publication describes an algorithm developed to determine the recommended staffing levels for clinical medical physics services in medical imaging and radionuclide therapy, based on current best practice, as described in international guidelines.

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This publication addresses costs arising during individual phases of an environmental remediation project, how they can be calculated, and how they can be structured and documented. It provides the methodology of cost estimation and includes examples of cost estimate models, development plans, cost elements and work breakdown structures. The guide also contains an overview of potentially suitable remediation technologies, which may help the reader to structure the options study.

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This publication provides information on detailed methodologies and examples in the application of volcanic hazard assessment to site evaluation for nuclear installations, thereby addressing the recommendations in IAEA Safety Standards Series No. SSG-21, Volcanic Hazards in Site Evaluation for Nuclear Installations. It demonstrates the practicability of evaluating the recommendations through a systematic volcanic hazard assessment and examples from Member States. The results of this hazard assessment can be used to derive the appropriate design bases and operational considerations for specific nuclear installations.

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This publication addresses the sustainability of all aspects of a national nuclear security regime, including those relating to nuclear material and nuclear facilities, other radioactive material and associated facilities, and nuclear and other radioactive material out of regulatory control. The publication is relevant for States that have established a nuclear security regime as well as for States that are in the process of establishing one. It includes guidance on how to address challenges in sustaining a nuclear security regime over time. It also addresses the initial development and implementation of the regime, particularly where sustainability can be built into it as part of its design.

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This publication provides guidance on assessing of sustainability of a nuclear energy system (NES) in the area of environmental impact of stressors. The INPRO methodology is a comprehensive tool for the assessment of sustainability of an NES. Basic principles, user requirements and criteria have been defined in different areas of the INPRO methodology. These include economics, infrastructure, waste management, proliferation resistance, environmental impact of stressors, environmental impact from depletion of resources, and safety of nuclear reactors and fuel cycle facilities. The ultimate goal of the application of the INPRO methodology is to check whether the assessed NES fulfils all the criteria, and hence the user requirements and basic principles, and therefore presents a system for a Member State that is sustainable in the long term.

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