Potential irradiation of Cu alloys and tungsten samples in DONES

Abstract

Tungsten and Cu alloys are currently proposed as reference candidate material for ITER and DEMO first wall and divertor. Tungsten is proposed for its high fusion temperature and CuCrZr alloys for their high thermal conductivity together good mechanical properties. However its behaviour under the extreme irradiation conditions as expected in ITER or DEMO fusion reactors is still unknown. Due to the determinant role of H and He played in the material behaviour any irradiation experiment must take into account the important amount of these gases produced during the irradiation in Fusion reactors with high-energy neutrons. DONES (DEMO Oriented Neutron Source) has been conceived as a simplified IFMIF (International Fusion Material Irradiation Facility) like plant to provide in a reduced time scale and with a reduced budget – both compared to IFMIF - the basic information on materials damage. The objective of DONES-IFMIF in its first stage will be to test structural materials under similar neutron irradiation nuclear fusion conditions as expected in fusion reactors. These tests will be carried out in specimens irradiated in the so called High Flux Test Module (HFTM). The objective of this paper is to assess on the potential use of DONES to irradiate Copper (Cu) alloys and Tungsten (W) in the HFTM together with other stainless steel based materials. The presence of Cu alloys or W specimens may have an effect in the irradiation parameters of the stainless steel samples placed also in the HFTM and in the samples of the Creep Fatigue Test Module (CFTM). McDeLicious code is used for neutron transport calculations. Damage dose rate and H and He production are analysed in the different locations and compared with the actual irradiation conditions in first wall and divertors in fusion machines.