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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)
Safety of New and Existing Research Reactor Facilities in Relation to Externa…
This book consist : Introduction; Safety concepts in siting and design; General approach to siting and design; Preliminary and final safety assessment; Site investigation; Evaluation of external hazards; Design, qualification and re-evaluation; Dispersion of radioactive material in the environment; Monitoring; Automatic scram and post-event operator action; Emergency procedures; and Quality ass…
Standard Format and Content for Safety Related Decommissioning Documents
This report provides information on the content and format for decommissioning plans and supporting safety related documents. Its scope includes information that is relevant to all types of nuclear facilities, ranging from nuclear power plants and reprocessing facilities to university laboratories and manufacturing plants. The report will be of interest to decommissioning planning engineers, pr…
Design of the Reactors Core for Nuclear Power Plants, Safety Guide
This book consist : Introduction; General safety considerations in design; Specific safety considerations in desgin; Qualification and testing; and Quality assurance in design. (Jml)
Safety Reports series No. 46: Assessment of defence in depth for nuclear powe…
This book consist : Introduction; The concept of defence in depth; Approach for making an inventory of the defence in depth capabilities of a plant; Applications; and Conclusions. (Jml)
Derivation of the Source Term and Analysis of the Radiological Consequences o…
This report provides a set of suggested methods and practices for determining the source term and analysing the radiological consequences of research reactor accidents. It provides safety analysts, regulators, and reactor facility management and operations staff, with the calculation methods and techniques necessary for deriving the source term. This includes all factors relevant to the formati…
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