Deterministic safety analysis (frequently 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. Requirements and guidance pertaining to the scope and content of accident analysis have been described in various IAEA publications. To a certain extent, accident analysis is covered in several publications of the revised Safety Standards Series, mainly in the Safety Requirements on design (Safety of Nuclear Power Plants: Design, Safety Standards Series No. NS-R-1) and in the Safety Guide on Safety Assessment and Verification for Nuclear Power Plants (Safety Standards Series No. NS-G-1.2). More detailed guidance has been included in the IAEA safety report on Accident Analysis for Nuclear Power Plants (Safety Reports Series No. 23). The safety report covers all the steps required for accident analyses (i.e. selection of initiating events and acceptance criteria, selection of computer codes and modelling assumptions, preparation of input data and presentation of the calculation results). The aforementioned safety standards and safety report recommend as one of the options for demonstrating the inclusion of adequate safety margins the use of best estimate computer codes with realistic input data in combination with the evaluation of uncertainties in the calculation results. For the evaluation of uncertainties, the sharing of experience and provision of guidance are elements of vital importance. This report has therefore been developed to complement the safety standards and the safety report referred to above. It provides more detailed information on the methods available for the evaluation of uncertainties in deterministic safety analysis for nuclear power plants and provides practical guidance in the use of these methods. This report is directed towards analysts coordinating, performing or reviewing best estimate accident analysis for nuclear power plants, both on the utility side and on the regulatory side. It also provides background material for relevant IAEA activities such as seminars, training courses and workshops. Thanks are due to V. Landauer for the preparation of the manuscript. The IAEA officer responsible for this publication was S. Lee of the Division of Nuclear Installation Safety.
Best Estimate Safety Analysis for Nuclear Power Plants: Uncertainty Evaluation. IAEA Safety Report Series
D'AURIA, FRANCESCO SAVERIO;
2008-01-01
Abstract
Deterministic safety analysis (frequently 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. Requirements and guidance pertaining to the scope and content of accident analysis have been described in various IAEA publications. To a certain extent, accident analysis is covered in several publications of the revised Safety Standards Series, mainly in the Safety Requirements on design (Safety of Nuclear Power Plants: Design, Safety Standards Series No. NS-R-1) and in the Safety Guide on Safety Assessment and Verification for Nuclear Power Plants (Safety Standards Series No. NS-G-1.2). More detailed guidance has been included in the IAEA safety report on Accident Analysis for Nuclear Power Plants (Safety Reports Series No. 23). The safety report covers all the steps required for accident analyses (i.e. selection of initiating events and acceptance criteria, selection of computer codes and modelling assumptions, preparation of input data and presentation of the calculation results). The aforementioned safety standards and safety report recommend as one of the options for demonstrating the inclusion of adequate safety margins the use of best estimate computer codes with realistic input data in combination with the evaluation of uncertainties in the calculation results. For the evaluation of uncertainties, the sharing of experience and provision of guidance are elements of vital importance. This report has therefore been developed to complement the safety standards and the safety report referred to above. It provides more detailed information on the methods available for the evaluation of uncertainties in deterministic safety analysis for nuclear power plants and provides practical guidance in the use of these methods. This report is directed towards analysts coordinating, performing or reviewing best estimate accident analysis for nuclear power plants, both on the utility side and on the regulatory side. It also provides background material for relevant IAEA activities such as seminars, training courses and workshops. Thanks are due to V. Landauer for the preparation of the manuscript. The IAEA officer responsible for this publication was S. Lee of the Division of Nuclear Installation Safety.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
