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 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 lithium flow target to test samples of candidate materials for fusion reactors.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 the facility reference design was provided, an activity aimed at the safety assessment of the target facility has been carried out applying the PRA (Probabilistic Risk Assessment) approach. The adopted methodology and calculation tool are respectively the fault tree and event tree technique, widely utilized in PRA studies, and RISK SPECTRUM code, a PC software package for system risk and reliability analysis. The paper at first gives a brief description of the IFMIF experimental plant and the target facility, reports the performed probabilistic safety analysis relative to the target and oriented to the accident sequences assessment and finally summarizes the obtained results.
Probabilistic Safety Analysis of IFMIF Target Facility
Burgazzi, L.
1999-04-19
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 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 lithium flow target to test samples of candidate materials for fusion reactors.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 the facility reference design was provided, an activity aimed at the safety assessment of the target facility has been carried out applying the PRA (Probabilistic Risk Assessment) approach. The adopted methodology and calculation tool are respectively the fault tree and event tree technique, widely utilized in PRA studies, and RISK SPECTRUM code, a PC software package for system risk and reliability analysis. The paper at first gives a brief description of the IFMIF experimental plant and the target facility, reports the performed probabilistic safety analysis relative to the target and oriented to the accident sequences assessment and finally summarizes the obtained results.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
