The Belgian Nuclear Research Centre SCK CEN launched the 1st phase implementation of MYRRHA reactor. This will deploy the construction of 100 MeV proton accelerator and complimentary research facilities including a dedicated station for irradiation of fusion materials (Fusion Target Station - FTS). This paper presents a baseline pre-conceptual design and analysis of the irradiation conditions for the most common in-vessel fusion materials i.e. tungsten and Eurofer97 steel. FTS will allow a direct irradiation by protons and/or irradiation via spallation neutron source. The former concept requires application of small specimen test techniques (SSTT), while the latter enable large irradiation volume with a limit damage rates. Both concepts are presented and discussed on the basis of achievable and yet meaningful irradiation conditions to complement the down selection and validation of new concepts of irradiation resistant materials.
|Title of host publication||Journal of Nuclear Materials: virtual special issues ICFRM 2019|
|Number of pages||17|
|State||Published - 1 May 2020|
|Event||2019 - ICFRM: The Nineteenth International Conference on Fusion Reactor Materials - HYATT regency La Jolla, La Joll|
Duration: 27 Oct 2019 → 1 Nov 2019
|Conference||2019 - ICFRM|
|Period||2019-10-27 → 2019-11-01|