29th Symposium on Fusion Technology (SOFT 2016)

P1.117 Advances of the Design Study of ITER-like divertor target for DEMO

5 Sep 2016, 14:20

1h 40m

Foyer 2A (2nd floor), 3A (3rd floor) (Prague Congress Centre)

Board: 117

Poster F. Plasma Facing Components P1 Poster session

Speaker

Fabio Crescenzi (Fusion and Technology for Nuclear Safety and Security)

Description

DEMO development is currently in the Pre-Conceptual Design Activity and the Divertor that is in charge of power exhaust and removal of impurity particles represents the key in-vessel component, with its Plasma Facing Units (PFU) exposed to the plasma and hence subjected to very high heat loads. During 2015 the integrated R&D project launched in the EUROfusion Consortium  studied how to approach and solve the many issues that DEMO will have to face: in fact unlike the ITER machine, DEMO will be subjected to an intense neutron irradiation that will cause damage and defects in the materials due to operation almost stationary during the envisaged lifetime of two full power years.      This paper deals with the advances in the design study of an “optimized” ITER-like Water Cooled Divertor able to withstand a stationary heat flux of 10MWm^-2-2,  as requested for DEMO operating conditions. The structural material for the heat sink pipe made in CuCrZr was assessed by means of a dedicated computational analysis procedure selecting appropriate ITER SDC-IC rules (3Sm and fatigue), together with the thermal margin to the local critical heat flux (CHF) at the cooling tube and the windows operating temperature for the material itself. The design rationale for the PFUs will be provided too. Further activities within the Eurofusion program foresee mock-up fabrication and high-heat-flux (HHF) tests.