ACCIDENT ANALYSIS FOR NUCLEAR POWER PLANTS WITH GRAPHITE MODERATED BOILING WA…

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Accident Analysis for Nuclear Power Plants with Graphite Moderated Boiling Wa…

This book consist : Introduction; Structural characteristics of RBMKs; Classification of initiating events; Acceptance criteria; Requirements for analysis; Selection of initial and boundary; Discussion of events; and Presentation of results. (Jml)

Design Measures to Facilitate Implementation of Safeguards at Future Water Co…

This book consist : Introduction; The IAEA's safeguards function for current and future nuclear power plants; Summary of the political and legal foundations of the IAEA's safeguards system; The technical objective of safeguards and the supply and use of required design information; Safeguards approaches for nuclear power plants; Design implications of experience in safeguarding nuclear power pl…

Nuclear Safety in Light Water Reactors: Severe Accident Phenomenology

Heavy-Water Power Reactors: Proceedings of a Symposium Vienna, 11-15 Septembe…

Heavy-water reactors have evoked a great deal of interest since the early days of atomic power development. These reactors, by virtue of their good neutron economy, offer certain advantages over other types, including lower fuel inventory, versatility in fuel cycle with the possibility of using natural or enriched uranium as well as thorium, better fuel utilization, and consequently low fuel cy…

Design Measures to FacilitateImplementation of Safeguards at Future Water Coo…

This report presents guidelines to the designers of water cooled power reactors which will minimize the impact of IAEA safeguards on plant operations and ensure efficient and effective acquisition of safeguards data to the mutual benefit of the Member State, the plant operator and the IAEA. These guidelines incorporate the IAEA's experience in establishing and carrying out safeguards at current…

Accident Analysis for Nuclear Power Plants with Pressurized Heavy Water React…

Deterministic safety analysis (henceforth referred to as accident analysis) is an important tool for confirming the adequacy and efficiency of provisions within the defence in depth concept for the safety of nuclear power plants (NPPs). Due to the close interrelation between accident analysis and safety, an analysis that lacks consistency, is incomplete or of poor quality is considered a safety…

Intercomparison of Techniques for Inspection and Diagnostics of Heavy Water R…

To foster international collaboration in nuclear power technology, the IAEA has conducted a coordinated research project (CRP) on Intercomparison of Techniques for Heavy Water Pressure Tube Inspection and Diagnostics. This publication presents the results of the second phase of the CRP, dealing with blister characterization by in situ non-destructive examination (NDE) techniques and determinati…

Safety Reports Series No. 30: Accident Analysis for Nuclear Power Plants with…

The objective of this publication is to provide specific guidance for accident analysis for nuclear power plants with pressurized water reactors, taking into account the specific design features of these reactors. This guidance covers all steps required to perform such analyses, including selection of initiating events, acceptance criteria, computer codes, modelling assumptions, preparation of …

Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reacto…

This Standard establishes the nuclear safety criteria and functional design requirements of structures, systems, and components of stationary pressurized water reactor (PWR) power plants. Operations, maintenance, and testing requirements are covered only to the extent that they affect design provisions.