Ponente
Descripción
Tungsten and Cu alloys are candidate armour materials for plasma-facing components, like the first wall and divertor, of ITER and future experimental nucler fusion power plant DEMO. Tungsten is selected for its high fusion temperature, for its unique resistance to ion and charge-exchange particle erosion and CuCrZr alloys for its high thermal conductivity together with good mechanical properties. However, the level of damage, as well as the amount of gas production, expected in the fusion reactors is such that the performance of materials and components under these extreme irradiation conditions is still unknown.
The scope of the International Fusion Irradiation Facility-DEMO Oriented NEutron Source (IFMIF-DONES) is to test materials under equivalent nuclear fusion irradiation conditions and doses to be qualified for the future nuclear fusion power plant DEMO.
This paper shows neutron transport calculations to assess the capability of IFMIF- DONES facility to irradiate copper alloys and tungsten in the High Flux Test Module (HFTM) in similar irradiation conditions to the ones expected in the future nuclear power plant. So far, the calculations of the irradiation condition in the High Flux Test Module (HFTM) were performed considering a dummy model of the rigs inner. The rigs are the containers inside the HFTM where the specimens will be held. However, in this work, the rigs are modelled using a detailed geometrical model of the sample distribution, which generate a more realistic calculation of the irradiation parameter expected in IFMIF-DONES facility.
