Probabilistic fault displacement hazard analysis (PFDHA) is a relatively new methodology, and actual examples of applications are quite limited. The current publication provides an introduction to probabilistic approaches to fault displacement hazard assessment with reference to relevant IAEA safety standards. It delineates the most important aspects of PFDHA (including up to date practices, open problems, and challenging issues) within a coherent framework. The information provided will be valuable not only for Member States when applying PFDHA to the site safety assessment of existing installations, but also for nuclear power plant operating organizations, regulatory bodies, vendors, technical support organizations and researchers working in the area of seismic hazard assessment.

This volume collects several extended articles from the first workshop on Best Practices in Physics-based Fault Rupture Models for Seismic Hazard Assessment of Nuclear Installations (BestPSHANI). Held in 2015, the workshop was organized by the IAEA to disseminate the use of physics-based fault-rupture models for ground motion prediction in seismic hazard assessments (SHA). The book also presents a number of new contributions on topics ranging from the seismological aspects of earthquake cycle simulations for source scaling evaluation, seismic source characterization, source inversion and physics-based ground motion modeling to engineering applications of simulated ground motion for the analysis of seismic response of structures. Further, it includes papers describing current practices for assessing seismic hazard in terms of nuclear safety in low seismicity areas, and proposals for physics-based hazard assessment for critical structures near large earthquakes. The papers validate and verify the models by comparing synthetic results with observed data and empirical models. The book is a valuable resource for scientists, engineers, students and practitioners involved in all aspects of SHA.

Diffuse seismicity refers to earthquakes occurring in locations where no apparent correlation can be made with any causative faults. This publication provides guidance for addressing the seismic hazard from diffuse seismicity in a manner consistent with internationally recognized practices and with reference to relevant IAEA safety standards.

This Safety Guide supersedes the 2010 edition of IAEA Safety Standards Series No. SSG-9. It takes account of recently gained knowledge and practices developed by Member States related to seismic hazards, especially lessons from the Fukushima Daiichi accident. It also addresses concomitant events associated with earthquakes, such as tsunamis. The revision provides a clearer separation between the process for assessing the seismic hazards at a specific nuclear installation site and the process for defining the related basis for design and safety assessment of the nuclear installation. Thus, it bridges gaps and avoids undue overlap of the two processes, which correspond to and are performed at different stages of siting of the nuclear installation.

Explaining the principles that underlie strong ground motion simulation, this publication describes various methods for simulating strong ground motions, and presents some examples of strong ground motion simulations using fault rupture modelling. The detailed guidelines and practical tools presented in this Safety Report will be of value to researchers, operating organizations, regulatory bodies, vendors and technical support organizations in the areas of seismic hazard evaluation of nuclear installations. The information provided will also be of great importance for seismic hazard assessments following the Fukushima Daiichi nuclear power plant accident.

The objective of this Safety Guide is to provide recommendations for meeting the IAEA safety requirements in performing or managing a level 2 probabilistic safety assessment (PSA) project for a nuclear power plant; thus it complements the Safety Guide on level 1 PSA. One of the aims of this Safety Guide is to promote a standard framework, standard terms and a standard set of documents for level 2 PSAs to facilitate regulatory and external peer review of their results. It describes all elements of the level 2 PSA that need to be carried out if the starting point is a fully comprehensive level 1 PSA. Contents: 1. Introduction; 2. PSA project management and organization; 3. Identification of design aspects important to severe accidents and acquisition of information; 4. Interface with level 1 PSA: Grouping of sequences; 5. Accident progression and containment analysis; 6. Source terms for severe accidents; 7. Documentation of the analysis: Presentation and interpretation of results; 8. Use and applications of the PSA; References; Annex I: Example of a typical schedule for a level 2 PSA; Annex II: Computer codes for simulation of severe accidents; Annex III: Sample outline of documentation for a level 2 PSA study.

Describes international approaches for maintaining fuel subcritical, removing residual heat, providing radiation protection and containing radioactive materials for the lifetime of a facility. It is intended to provide details on the safety assessment of interim spent fuel storage facilities that are not an integral part of an operating plant.

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.