Deterministic Safety Analysis
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Deterministic Safety Analysis for Nuclear Power Plants
The objective of this Safety Guide is to provide harmonized guidance to designers, operators, regulators and providers of technical support on deterministic safety analysis for nuclear power plants. It provides information on the utilization of the results of such analysis for safety and reliability improvements. The Safety Guide addresses conservative, best estimate and uncertainty evaluation approaches to deterministic safety analysis and is applicable to current and future designs. Contents: 1. Introduction; 2. Grouping of initiating events and associated transients relating to plant states; 3. Deterministic safety analysis and acceptance criteria; 4. Conservative deterministic safety analysis; 5. Best estimate plus uncertainty analysis; 6. Verification and validation of computer codes; 7. Relation of deterministic safety analysis to engineering aspects of safety and probabilistic safety analysis; 8. Application of deterministic safety analysis; 9. Source term evaluation for operational states and accident conditions; References.
Deterministic Safety Analysis for Nuclear Power Plants
Author: International Atomic Energy Agency
language: en
Publisher: International Atomic Energy Agency
Release Date: 2019-09-24
Deterministic safety analysis is an essential component of safety assessment, particularly for safety demonstration of the design of nuclear power plants (NPPs). The objective of deterministic safety analysis is to confirm that safety functions can be fulfilled and that the necessary structures, systems and components, in combination with operator actions, are effective in keeping the releases of radioactive material from the plant below acceptable limits. Deterministic safety analysis, supplemented by further specific information and analysis, including probabilistic safety analysis, is also intended to demonstrate that the source term and the potential radiological consequences of different plant states are acceptable, and that the possibility of certain conditions arising that could lead to an early or a large radioactive release can be considered as 'practically eliminated'. The publication has been updated to maintain consistency with current IAEA safety requirements and to reflect lessons from the Fukushima Daiichi accident. It takes into account current practices and experience from deterministic safety analyses for NPPs being performed around the world.
Safety Analysis and Licensing Documentation for Nuclear Fuel Cycle Facilities
Author: IAEA
language: en
Publisher: International Atomic Energy Agency
Release Date: 2020-06-05
This publication gives practical information and examples of 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 relicensing process.