IAEA Nuclear Energy Series

In the context of the safe management of disused sealed radioactive sources, an important and emerging issue of immediate concern is the management of depleted uranium (DU) contained in radiation shielding materials, as potential radioactive waste. This publication presents relevant information on technical issues and factors, as well as specific Member State experiences leading to the identification of potential options for the management of DU shields. Various options for safe, secure and cost-effective solutions have been explored, ranging from returning to manufacturer, including reuse, recycling, storage and disposal in licensed facilities.

Major accidents at a nuclear power plant or fuel cycle facility are rare but can produce large quantities of radioactive waste with widely varying characteristics that can be difficult to manage. Large volumes of radioactive waste can also be generated by accidents at military installations or by the mishandling high-activity-sealed radiation sources. In the case of a major accident, radioactive waste volumes may quickly overwhelm existing national management and disposal infrastructure. Appropriate disposal facilities might not be available to match the amounts or characteristics of the wastes. This publication is developed to support Member States efforts towards improved preparedness related to the management of radioactive waste in the event of a nuclear or radiological accident. It builds on experiences gained following historic accidents to develop lessons learned, which planners in governmental agencies and nuclear facilities are encouraged to consider in preplanning activities.

Reliable methods for estimating the cost of a radioactive waste disposal programme are crucial to ensure that the necessary funding for completing the disposal programme is available. Estimating the cost for disposal is, however, a challenging and complex task. Disposal programmes themselves are complex and long term undertakings, and conditions can be expected to change significantly over the time span during which a disposal programme is developed and implemented. This publication provides Member States with information on developing cost estimates for a disposal programme and establishing funding mechanisms. It will help readers in becoming informed clients by familiarizing themselves with the approaches and complexities in cost estimates and funding mechanisms for disposal. The publication is applicable to all waste categories and both near surface and geological disposal. It contains relevant examples and case studies from national programmes. The cost figures are intended to give an indication of the possible cost of certain parts or aspects of the disposal programme rather than to compare different disposal programmes’ costs.

Member States intending to introduce a nuclear power programme will need to pass through several phases during the implementation. Experience shows that careful planning of the objectives, roles, responsibilities, interfaces and tasks to be carried out in different phases of a nuclear project is important for success. This publication presents a harmonized approach that may be used to structure the owner/operator management system and establish and manage nuclear projects and their development activities irrespective of the adopted approach. It has been developed from shared management practices and consolidated experiences provided by nuclear project management specialists through a series of workshops and working groups organized by the IAEA. The resultant publication presents a useful framework for the management of nuclear projects from initiation to closeout and captures international best practices.

Communication and stakeholder involvement are essential components for a successful disposal program. Experience around the world suggests that the scientific and technological bases for the safe disposal of radioactive waste are available — disposal solutions exist or can be developed based on established knowledge. However, concerns and opposition among the public and other stakeholders could slow or even prevent the implementation of needed disposal solutions. This publication provides practical guidance on communication and stakeholder involvement for countries embarking on, relaunching or revising a disposal programme. It draws upon past experiences and emphasizes that practical implementation requires adjusting to the evolving context as given by the national, social and political circumstances. The primary intended users of this publication include those working in the field of radioactive waste management in government, regulatory bodies and industry, and especially in organizations responsible to implement solutions for radioactive waste disposal.

It was formerly hypothesized that placing a radioactive source near the end of a lightning conductor would improve the likelihood that lightning would strike the conductor. It is estimated that hundreds of thousands of these radioactive lightning conductors (RLCs) were installed worldwide. However, no convincing scientific evidence has been produced to demonstrate increased efficacy and the use of RLCs does not comply with the justification principle established in the International Basic Safety Standards. Therefore, most countries have recognized the need to stop installing RLCs and to remove existing devices from the public domain. This publication summarizes all technical and organizational aspects related to the recovery and dismantling of RLCs as well as the safe management of the associated disused radioactive sources. The report describes the general arrangement, highlights the quality management components, identifies the staffing requirements and covers certain areas vital for the preparation for dismantling and source conditioning operations. Relevant information is provided on the various models of radioactive lightning conductors and how their design features influence the dismantling and source recovery operations. The publication also incorporates the most recent experience on various concluded projects in several Member States and captures the lessons learned.

Training is an important tool to achieve and maintain the required competence of personnel working in nuclear facilities. Effective training and qualification of personnel are necessary for the achievement of high safety and efficiency standards in nuclear facility performance. Training and qualification combined is a key feature of the integrated management systems of nuclear facilities. It is these considerations that led to this publication which consolidates the experience gained worldwide using the systematic approach to training (SAT) for nuclear facility personnel. It provides a basis for establishing and sustaining the quality and reliability of training and qualification for all main categories of nuclear facility personnel. SAT has proved its effectiveness in nuclear and other safety critical industries over decades and is recognized as the best international practice in nuclear training. The publication details the processes and methodology, presents good practices and offers recommendations from the experts in the field on the entire set of activities within the SAT–based training methodology and provides examples of SAT application. It builds on, and supersedes, guidance provided in an earlier IAEA publication (Technical Report Series 380, Nuclear Power Plant Personnel Training and its Evaluation: A Guidebook). A key feature of this publication is demonstrating how SAT–based training serves as one of the important processes in a nuclear facility management system and how it integrates with other processes.

The terms for describing advanced nuclear power plants (NPPs) need to conform to the broad, general, common understanding by the public as well as by the technical community. This publication is a revision of IAEA-TECDOC-936 incorporating developments and initiatives since 1997 in the areas of advanced, evolutionary, and innovative nuclear reactor designs, description of design development phases, inclusive of relevant safety and regulatory terminology, consistent with current IAEA safety standards and glossaries. The objective of this publication is to provide Member States with up-to-date terms for describing advanced NPPs, to draw distinctions between design phases reflecting the maturities of designs, and to clarify definitions of commonly used terms in describing advanced NPPs.

A considerable level of international experience has been gained over the last decades in designing radioactive waste disposal facilities. This publication is intended to assist Member States in planning for the disposal of radioactive waste. Specifically, this publication describes the approaches and principles to be considered by the responsible organizations within a Member State involved in the planning and design of radioactive waste disposal facilities. Examples are provided for all waste classes requiring disposal. The examples are based on successfully implemented designs or on design concepts that are sufficiently advanced to demonstrate their overall feasibility for the safe disposal of radioactive waste. Alternate disposal options are also discussed, describing solutions that rely on the conversion of existing facilities, such as mines or other underground openings as well as the potential for disposal in boreholes.

This publication explains how a reactor technology assessment is performed and how the process and its results enable decision making for nuclear power planning and implementation at each of its phases. The methodology has been revised to incorporate developments since the first edition in 2013 and includes feedback from comprehensive training workshops offered for the last six years to Member States introducing nuclear power programmes. The aim of this publication is to help newcomer Member States to understand the complexity involved in the selection of the most suitable reactor technology as well as obligations and responsibilities integral to an unbiased assessment. The publication can also be used by countries that already have nuclear power programmes, to assist in their selection of the next nuclear power plant.

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.

This publication documents the results of an IAEA coordinated research project (CRP)on the application of computational fluid dynamics (CFD) codes for nuclear power plant design. The main objective was to benchmark CFD codes, model options and methods against CFD experimental data under single phase flow conditions. This publication summarizes the current capabilities and applications of CFD codes, and their present qualification level, with respect to nuclear power plant design requirements. It is not intended to be comprehensive, focusing instead on international experience in the practical application of these tools in designing nuclear power plant components and systems. The guidance in this publication is based on inputs provided by international nuclear industry experts directly involved in nuclear power plant design issues, CFD applications, and in related experimentation and validation highlighted during the CRP.

This publication reports on the DACCORD project, which supports Member States in preparing preliminary cost estimates for the decommissioning of research reactors. The report is of particular benefit to programmes with limited decommissioning experience. Costing projects for the decommissioning of research reactors can be broad in scope with many possible inputs and influences that require due consideration in developing the estimate. The publication provides information on unit factors for research reactor decommissioning and a basis for estimating uncertainties and contingencies and for assessing the impact of decommissioning planning and characterization activities. It also addresses the use of the CERREX-D2 (Cost Estimate for Research Reactors in Excel) software code, developed by the IAEA to enable non-specialist users to develop preliminary cost estimates for decommissioning.

Technology roadmaps have proven to be a useful management tool for evaluating, planning and strategizing the development of complex technological projects. This publication is intended to provide Member States with a set of generic roadmaps which can be used in the deployment of small modular reactors. These roadmaps are based on the latest inputs from Member States currently pursuing this technology. The publication places emphasis on the activities of owners/operators who drive the demand and requirements for the reactor designs, the designers who develop the technologies, and the regulators who establish and maintain the regulatory requirements that owners/operators should meet. It also provides a methodology for developing a technology roadmap for reactors with longer development horizons and discusses emerging opportunities and challenges for this relatively new technology.

Many IAEA Member States have expressed interest in introducing or reintroducing uranium mining and related activities for the purposes of nuclear fuel production, and so contribute to meeting energy needs. This publication is intended to be used as guidance on how to evaluate the progress toward establishing or re-establishing a national uranium production programme and to aid in the planning steps necessary to develop the national infrastructure requirements for uranium production in a Member State. The publication includes consideration of four phases of successive development in the uranium production cycle to achieve four corresponding milestones. The four phases are: (i) exploration, (ii) construction/ commissioning of a uranium mine and processing facility, (iii) safe operation of a uranium mine and processing facility, and (iv) decommissioning and remediation. Within each phase sixteen aspects or issues are identified that ought to be addressed to achieve each milestone in the development of the uranium production cycle. The publication will be of interest to government decision makers and decision influencers, such as advisors in relevant government departments, regulatory bodies involved in regulation of uranium mines and processing facilities, and the uranium mining/processing industry and researchers.

This publication presents the outcomes of a collaborative study to analyse the status of nuclear decommissioning activities around the world as of 2020. Future evolution of these activities was also considered. The information presented is based on responses to a questionnaire distributed to organizations with responsibility for planning, implementation and oversight of decommissioning programmes, with baseline information on the numbers and current operational status of nuclear facilities being extracted from the online nuclear facilities databases maintained by IAEA. Analysis of the collected data was undertaken at global and regional levels, rather than at the level of individual States or facility sites. The publication is intended primarily to be of use to individuals with policy responsibilities in the area of decommissioning and associated waste management activities, including government officials, regulators, facility manages and service providers.

This publication is part of a series that aims to inform nuclear facility designers, vendors, operators and State governments about IAEA safeguards and how associated requirements can be considered early in the design phase of a new nuclear facility. This particular publication is applicable to the design of spent nuclear fuel reprocessing plants. Safeguards by design dialogue undertaken early in the design and construction of reprocessing plants, facilitates the implementation of safeguards throughout all the life cycle 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.

Research reactor fuel technology continues to evolve, driven in part by international efforts to develop high density fuels to enable the conversion of more reactors from highly enriched uranium (HEU) to low enriched uranium (LEU) fuels. These high density fuels may offer economic benefits for research reactors, despite being more expensive initially, because they offer the prospect of higher per-assembly burnup, thus reducing the number of assemblies that must be procured, and more flexibility in terms of spent fuel management compared to the currently qualified and commercially available LEU silicide fuels. Additionally, these new fuels may offer better performance characteristics. This publication provides a preliminary evaluation of the impacts on research reactor performance and fuel costs from using high density fuel. Several case studies are presented and compared to illustrate these impacts.

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.

In recent years, several Member States have completed the decommissioning of multifacility nuclear sites. This publication consolidates their technical and organizational experience, and provides information and practical guidance that promotes safe, timely and cost effective implementation. All phases of decommissioning are discussed, from planning and dismantling to waste management and site release, as well as organizational schemes and funding. This publication is intended for decision makers, plant operators, contractors and regulators involved in planning, management, authorization and execution of decommissioning activities. It is particularly relevant for multifacility site operators with nuclear facilities approaching the end of their foreseen lifetime. The publication will also be of interest for the designers and builders of new nuclear installations in order to facilitate eventual decommissioning.

This publication provides a global overview of the status of spent fuel and radioactive waste management programmes, inventories, current practices, technologies and trends. It presents information on national arrangements for the management of spent fuel and radioactive waste, and on current waste and spent fuel inventories and their future estimates. Achievements, challenges and trends in the management of spent fuel and radioactive waste are also addressed. This second edition has been developed with a basis of national profiles submitted by Member States, complemented with openly available Joint Convention National Reports. The data reported are fully dependent on the input from the States and by the assumptions made to transform these data into the waste classes defined in IAEA Safety Standards Series No. GSG-1, Classification of Radioactive Waste.

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 publication also contains an overview of potentially suitable remediation technologies, which may help the reader to structure the options study.

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.

The transition to digital technology has changed the nature of instrumentation and control (l&C) systems by enabling extensive interconnection of reprogrammable, functionally interdependent I&C systems. This development has made computer security a necessary element for consideration in I&C system design. The benefits and challenges of the various computer security methods and controls with their implementation in nuclear power plant I&C systems are discussed and described in this publication. The publication provides an overview of current knowledge, up to date good practices, experience, and benefits and challenges related to the application of computer security measures. The publication defines the key concepts for computer security for I&C systems at nuclear facilities, explains the risk informed approach to computer security and describes how computer security measures are applied throughout the l&C system life cycle. Situations where I&C systems are interconnected with enterprise management systems are also addressed. The three appendices present case studies with practical application examples.

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 publication also contains an overview of potentially suitable remediation technologies, which may help the reader to structure the options study.

This publication describes the purpose and scope of the INPRO service Analysis Support for Enhanced Nuclear Energy Sustainability (ASENES) and its potential benefits to Member States. The publication highlights the links between this service and overall technical support to Member States for the planning and development of nuclear energy, and explains how it integrates with other IAEA services supporting knowledgeable decision making on nuclear power. An overview of analytical tools developed by INPRO for this purpose is also provided.

This publication provides guidance on the management of human resources in the field of nuclear energy. It considers this issue at both the individual and organizational level, and the development of an appropriate human resource management (HRM) strategy. It elaborates on ten key HR processes concerning the management of individual employees, as well as the four broader organizational issues – organizational and safety culture, stakeholder engagement, diversity and inclusion, and change management – to which they relate. It describes the importance of having a correct HRM strategy is in place, together with the right level of competent resources, effective processes, and procedures, to support the needs of nuclear organizations.

Recent decades have seen a significant increase in the number of decommissioning projects undertaken globally. Decommissioning technologies have advanced, driven by innovations in digitization and robotics, and the Systematic Approach to Training (SAT) methodology is now being applied to the decommissioning phase of all types of nuclear facilities. This publication provides practical information and examples of good practices in training personnel for decommissioning activities, based on Member States’ experience, including guidance on the application of SAT methodology. The increasing use of digital and web-based tools to enhance competence development for implementation of decommissioning programmes is also discussed.

This publication, which draws upon the outcome of an IAEA coordinated research project, presents methodologies for assessing pipe failure rates in advanced water cooled reactors (WCRs), including a comprehensive review of good practices for the assessment of piping reliability parameters for advanced WCRs. Good practices are those processes and analytical tasks that would be expected in piping reliability analysis in order for the results to be realistic representations of piping structural integrity. This publication builds on technical insights that have been obtained using different methodologies when applied in multiple analytical contexts and responding to the requirements of different national codes and standards. It provides Member States with a strong technical basis for establishing design and plant centric piping reliability parameters for input into probabilistic safety assessment studies, in-service inspection programme development, and operational support. Additionally, an objective evaluation and inter-comparison of methods used in participating Member States is outlined leading to a harmonization of the practices relevant to newly deployable advanced WCRs.

Nuclear cogeneration to produce electricity and process heat for nonelectric applications such as desalination, district heating or cooling or hydrogen production can play an important role in reducing dependence on fossil fuels. The implementation of nuclear cogeneration projects is inherently complex and such projects require a clear understanding of actions and responsibilities during the design, operation and management phases. This publication focuses on analysing the requirements and responsibilities of users and vendors and correspondence between them through the life cycle to of a nuclear cogeneration project, highlighting experience and lessons learned from retrofit and new build projects.