This publication provides specific recommendations on research reactor instrumentation and control systems and software important to safety, including instrumentation and control system architecture and associated components, from sensors to actuators, operator interfaces and auxiliary equipment, to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. The recommendations and guidance apply to both the design and configuration management of instrumentation and control systems for new research reactors and the modernization of the instrumentation and control systems at existing research reactor facilities. In addition, this Safety Guide provides recommendations and guidance on human factors engineering and human-machine interfaces, and for computer based systems and software for use in instrumentation and control systems important to safety. This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-37, which it supersedes.

This Safety Guide provides recommendations on the operating organization and on personnel for research reactors to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. It covers the typical operating organization for research reactor facilities; the recruitment process and qualification in terms of education, training and experience; programmes for initial and continuing training; the authorization process for those individuals having an immediate bearing on safety; and the processes for their requalification and reauthorization. This Safety Guide is a revision of IAEA Safety Standards Series No. NS-G-4.5, which it supersedes.

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.

This publication defines a framework that represents the state of the art in assessment methodologies for safety and instrumentation and control software used at nuclear power plants. It describes an approach for developing and communicating assessments based on claims, argument and evidence. The assessment of software dependability, which encompasses properties such as safety, reliability, availability, maintainability and security, is an essential and challenging aspect of the safety justification. Guiding principles for a dependability assessment are established to provide the basis for defining an assessment strategy and implementing the assessment process. Sources of evidence for the assessment are provided and lessons learned from past digital instrumentation and control system implementation in areas such as software development, operational usage, regulatory review and platform certification are also described.

Plant Hazard Analysis and Safety Instrumentation Systems is the first book to combine coverage of these two integral aspects of running a chemical processing plant. It helps engineers from various disciplines learn how various analysis techniques, international standards, and instrumentation and controls provide layers of protection for basic process control systems, and how, as a result, overall system reliability, availability, dependability, and maintainability can be increased. This step-by-step guide takes readers through the development of safety instrumented systems, also including discussions on cost impact, basics of statistics, and reliability. Swapan Basu brings more than 35 years of industrial experience to this book, using practical examples to demonstrate concepts. Basu links between the SIS requirements and process hazard analysis in order to complete SIS lifecycle implementation and covers safety analysis and realization in control systems, with up-to-date descriptions of modern concepts, such as SIL, SIS, and Fault Tolerance to name a few. In addition, the book addresses security issues that are particularly important for the programmable systems in modern plants, and discusses, at length, hazardous atmospheres and their impact on electrical enclosures and the use of IS circuits. - Helps the reader identify which hazard analysis method is the most appropriate (covers ALARP, HAZOP, FMEA, LOPA) - Provides tactics on how to implement standards, such as IEC 61508/61511 and ANSI/ISA 84 - Presents information on how to conduct safety analysis and realization in control systems and safety instrumentation

This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-24, which it supersedes. The current publication provides recommendations on how to meet the applicable safety requirements relating to the utilization and modification of research reactors. The recommendations focus on the categorization, safety assessment and approval of research reactor experiments and modification projects. The publication also incorporates the relevant lessons learned from the accident at the Fukushima Daiichi nuclear power plant and elaborates on interfaces between nuclear safety and nuclear security. Specific safety considerations in different phases of utilization and modification projects are covered, including pre­implementation, implementation, and post implementation phases. Guidance is given on operational safety of experiments, including the handling, dismantling, post-irradiation examination and disposal of experimental devices. The publication is intended to be of use to individuals within the operating organizations of research reactors, regulatory bodies, as well as the experimenters, technical support organizations and other persons involved in utilization and modification projects.