IAEA (International Atomic Energy Agency) Safety Guide SSG-2 provides recommendations and guidance on the use of deterministic safety analysis and its application to nuclear power plants in compliance with the IAEA’s Safety Requirements publications on Safety of Nuclear Power Plants: Design and Safety Assessment for Facilities and Activities. Current developments for ensuring the stable, safe and competitive operation of nuclear reactors are closely related to the advances that are being made in safety analysis. Deterministic safety analyses for anticipated operational occurrences, design basis accidents (DBAs) and beyond design basis accidents (BDBAs), are essential instruments for confirming the adequacy of safety provisions. Initially, rigorous conservative approaches to anticipated operational occurrences and design basis accidents were used in deterministic safety analyses. Licensing calculations used conservative codes with conservative input data, mostly owing to the difficulty of modelling complicated physical phenomena with limited computer capacity and a lack of adequate data. As more experimental data have become available, and with advances in code development, for loss of coolant accidents (LOCAs) in particular, the practice in many States has moved towards a more realistic approach together with an evaluation of uncertainties. This is termed a best estimate approach.
IAEA SSG-2 Deterministic Safety Analysis for NPP
D’Auria F.
Co-primo
Methodology
;
2010-01-01
Abstract
IAEA (International Atomic Energy Agency) Safety Guide SSG-2 provides recommendations and guidance on the use of deterministic safety analysis and its application to nuclear power plants in compliance with the IAEA’s Safety Requirements publications on Safety of Nuclear Power Plants: Design and Safety Assessment for Facilities and Activities. Current developments for ensuring the stable, safe and competitive operation of nuclear reactors are closely related to the advances that are being made in safety analysis. Deterministic safety analyses for anticipated operational occurrences, design basis accidents (DBAs) and beyond design basis accidents (BDBAs), are essential instruments for confirming the adequacy of safety provisions. Initially, rigorous conservative approaches to anticipated operational occurrences and design basis accidents were used in deterministic safety analyses. Licensing calculations used conservative codes with conservative input data, mostly owing to the difficulty of modelling complicated physical phenomena with limited computer capacity and a lack of adequate data. As more experimental data have become available, and with advances in code development, for loss of coolant accidents (LOCAs) in particular, the practice in many States has moved towards a more realistic approach together with an evaluation of uncertainties. This is termed a best estimate approach.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
