A neutron irradiation facility is planned as International Fusion Materials Irradiation Facility (IFMIF) under the collaborative program of International Energy Agency (IEA) Implementing Agreement for a Program of Research and Development on Fusion Materials. The experimental facility produces neutrons with peak energy of around 14 MeV by D-Li reactions by a high current deuteron linear accelerator and a high speed Li flow target to test and qualify fusion reactor materials. In the frame of the Conceptual Design Evaluation (CDE) phase (1997-98), following the Conceptual Design Activity (CDA) completed at the end of 1996 in which plant reference design was provided, an activity aimed at the safety assessment of the entire IFMIF plant and its subsystems (Test Cell, Target, Accelerator and Conventional Facilities) has been performed using the Probabilistic Risk Assessment (PRA) methodology. The adopted methodology and calculation tool are respectively the fault tree and event tree technique, widely utilized in the PRA studies, and RISK SPECTRUM code, a PC software package for system risk and reliability analysis. The paper reports the foregoing probabilistic safety analysis extended to the whole IFMIF plant focusing particularly on the accident sequence analysis, summarizes the obtainezd results and provides an uncertainty and sensitivity analysis.
Probabilistic Safety Assessment of IFMIF Plant
Burgazzi, L.
1999-08-22
Abstract
A neutron irradiation facility is planned as International Fusion Materials Irradiation Facility (IFMIF) under the collaborative program of International Energy Agency (IEA) Implementing Agreement for a Program of Research and Development on Fusion Materials. The experimental facility produces neutrons with peak energy of around 14 MeV by D-Li reactions by a high current deuteron linear accelerator and a high speed Li flow target to test and qualify fusion reactor materials. In the frame of the Conceptual Design Evaluation (CDE) phase (1997-98), following the Conceptual Design Activity (CDA) completed at the end of 1996 in which plant reference design was provided, an activity aimed at the safety assessment of the entire IFMIF plant and its subsystems (Test Cell, Target, Accelerator and Conventional Facilities) has been performed using the Probabilistic Risk Assessment (PRA) methodology. The adopted methodology and calculation tool are respectively the fault tree and event tree technique, widely utilized in the PRA studies, and RISK SPECTRUM code, a PC software package for system risk and reliability analysis. The paper reports the foregoing probabilistic safety analysis extended to the whole IFMIF plant focusing particularly on the accident sequence analysis, summarizes the obtainezd results and provides an uncertainty and sensitivity analysis.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
