This publication presents the outputs of the INPRO collaborative project ROADMAPS. It introduces the concept of roadmapping for enhanced nuclear energy sustainability, which has been developed over the course of several collaborative projects within INPRO. The principal products of the ROADMAPS collaborative project are the roadmap template and the ROADMAPS-ET tool. ROADMAPS-ET is an analytical decision support tool for structuring, unifying and visualizing data on issues related to long term nuclear energy planning and nuclear energy system sustainability enhancement. It is supplemented by an approach for the bottom-up integration of national roadmaps. The publication includes case studies which are trial applications of the roadmap template. The studies address national or cooperative long term nuclear energy deployment scenarios with evolutionary as well as with innovative nuclear energy technologies. Examples of possible roadmap aggregation for analysis at regional and global levels are also provided.

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.

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.

The assessment approach described in this publication provides a comprehensive means to determine the status of the infrastructure conditions relevant to all issues detailed in IAEA Nuclear Energy Series No. NP-T-5.1, Specific Considerations and Milestones for a Research Reactor Project. This approach can be used by any interested Member State for self-assessment to identify weaknesses and to determine the additional work needed to develop its national nuclear infrastructure for research reactor programme to an appropriate level. Member States planning to embark on both a research reactor programme and a nuclear power programme, may refer to this publication to ensure that the approach and methodology for the implementation of both programmes is harmonized, efficient and effective.

Within the nuclear field, a vast body of knowledge, involving scientific, technical and managerial fields, is distributed among many organizations of different types. Managing and provisioning distributed knowledge is therefore becoming one of the major challenges in federated organizational environments. This publication provides information to organizations dealing with nuclear knowledge and its management. It covers an introduction to semantic information technologies, the Worldwide Web standards developed for interoperability, the construction of knowledge bases on the basis of distributed knowledge, and the development of knowledge driven applications. In addition to providing insight into the development of distributed knowledge bases, the intent of this publication is to provide examples of applications of semantic technologies specifically in the nuclear field.

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.

IAEA work in the area of research reactor operation and maintenance is aimed at enhancing the capabilities of Member States to utilize good engineering and management practices to improve research reactor reliability and availability. In particular, the IAEA supports activities addressing ageing management of research reactor instrumentation and control (I&C) systems. The purpose of this publication is to provide engineering guidance on the design, and operational aspects of digital I&C systems for the refurbishment of existing facilities and for new research reactors. Key areas addressed include codes and standards applicability, licensing issues, dealing with the change in human-system interface from analogue to digital technology, software verification and validation activities, periodic testing and inspection, and configuration management. The publication contains technical descriptions and summaries of available digital systems that have been utilized in both new research reactor designs, and in the upgrading of older analogue safety and control systems. This guidance is foreseen for the broad spectrum of research reactors types existing today.

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.

Asset management plays an important role in maintaining the competitiveness of nuclear power plants in a challenging and changing electricity market. The value of effective asset management is in providing support to those making decisions seeking the optimum level of financial performance, operational performance and risk exposure. This publication provides information on various methodologies, good practices and approaches to manage assets in nuclear power plants currently in operation or in other operational nuclear facilities. Information relevant to new build and decommissioning environments is also provided.

This publication outlines the concepts and models supporting the requirements for understanding organizational competence within the nuclear context. It aims to help in the development of organizational competencies in countries with an existing nuclear power capability and those wishing to embark on a nuclear power programme. The publication summarizes necessary processes for mapping organizational competencies, as well as tools and techniques used for assessing them. Specific information provided in this publication will help organizations to determine competence needs based on strategic/corporate objectives and business processes, and to identify their existing success factors.