The International Fusion Materials Irradiation Facility (IFMIF) is an international joint project aimed at developing an accelerator-based neutron irradiation facility to test and qualify candidate materials to be used in future fusion power reactors. Within the current IFMIF Engineering Validation and Engineering Design Activities (EVEDA) phase, ENEA is involved in the design of the Target Assembly (TA) with removable bayonet Backplate which is one of the two alternative concepts envisaged for the TA system of IFMIF (the other being the Integral Target Assembly to be developed by JAEA in Japan). In the present annual period covered by the current MSE-ENEA Agreement, the design of the Target Assembly with bayonet Backplate has advanced starting from a reference model based on the previous design which was described in the system Design Description Document of the Engineering Design Activities phase I (DDD-I). In particular, the integration of the Target Assembly with bayonet Backplate into the Li loop and Target Test Cell models has been performed. Moreover, some important features previously not present in the model, such as the TA supporting structures and positioning system and the thermal compensating system were developed and introduced in the design. As a further advancement, some work has been done on the numerical analyses in support to the TA design and the safety assessment of the IFMIF Lithium Target Facility that is also a task in charge of ENEA within the IMIF/EVEDA project. Regarding this latter activity, a contribution has been given to the preparation of the IFMIF main safety documents. Updated activation calculations for the Activated Corrosion Products (ACP) have been also performed in order to provide the radioactive inventories of Lithium containing ACP due to the irradiation of both neutron and deuteron fluxes. Concerning the numerical analyses, the work performed has been mainly devoted to setting up the software tools (in particular the McCad interface software) to perform the neutronic analysis of the integrated TA model, that will be carried out in the next phase of the project. Calculations of the power deposition of Deuteron beams in the Lithium jet, which is needed for thermo-hydraulics calculations, have been also performed. In the present document, a detailed description of all the above mentioned activities is reported. Moreover, a rough cost evaluation of the TA system with bayonet Backplate is also given.

Rapporto preliminare del progetto del target di IFMIF comprensivo di disegni, analisi numeriche e valutazione dei costi

Serra, M.;Porfiri, M.T.;Pinna, T.;Miccichè, G.;Frisoni, M.;Bernardi, D.
2012

Abstract

The International Fusion Materials Irradiation Facility (IFMIF) is an international joint project aimed at developing an accelerator-based neutron irradiation facility to test and qualify candidate materials to be used in future fusion power reactors. Within the current IFMIF Engineering Validation and Engineering Design Activities (EVEDA) phase, ENEA is involved in the design of the Target Assembly (TA) with removable bayonet Backplate which is one of the two alternative concepts envisaged for the TA system of IFMIF (the other being the Integral Target Assembly to be developed by JAEA in Japan). In the present annual period covered by the current MSE-ENEA Agreement, the design of the Target Assembly with bayonet Backplate has advanced starting from a reference model based on the previous design which was described in the system Design Description Document of the Engineering Design Activities phase I (DDD-I). In particular, the integration of the Target Assembly with bayonet Backplate into the Li loop and Target Test Cell models has been performed. Moreover, some important features previously not present in the model, such as the TA supporting structures and positioning system and the thermal compensating system were developed and introduced in the design. As a further advancement, some work has been done on the numerical analyses in support to the TA design and the safety assessment of the IFMIF Lithium Target Facility that is also a task in charge of ENEA within the IMIF/EVEDA project. Regarding this latter activity, a contribution has been given to the preparation of the IFMIF main safety documents. Updated activation calculations for the Activated Corrosion Products (ACP) have been also performed in order to provide the radioactive inventories of Lithium containing ACP due to the irradiation of both neutron and deuteron fluxes. Concerning the numerical analyses, the work performed has been mainly devoted to setting up the software tools (in particular the McCad interface software) to perform the neutronic analysis of the integrated TA model, that will be carried out in the next phase of the project. Calculations of the power deposition of Deuteron beams in the Lithium jet, which is needed for thermo-hydraulics calculations, have been also performed. In the present document, a detailed description of all the above mentioned activities is reported. Moreover, a rough cost evaluation of the TA system with bayonet Backplate is also given.
Nuclear fusion;ITER Project
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.12079/6316
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