In-vessel Components For ITER Research Articles

The effect of irradiation on tensile properties and fracture toughness of CuCrZr and CuCrNiSi alloys

This paper deals with the effect of irradiation on tensile properties and fracture toughness of CuCrZr and CuCrNiSi alloys, considered for use in some in-vessel components of ITER, where a combination of high strength and heat conduction is essential. The heat treatments were:–CuCrZr, quenching in water after annealing at 950°С, cold worked 40–45%, and aged at 475–500°С for 3h.–CuCrNiSi, quenching in water after annealing at 980°С and aged for 4h at 460°С.Specimens were irradiated in the IVV-2 reactor at ∼200°С and with irradiation damage of 0.15 and 0.27dpa. Post-irradiation tests were carried out to assess the tensile properties and fracture toughness of the materials. The tests results show that CuCrNiSi has better strength and retains higher ductility after irradiation, but has somewhat lower crack resistance than CuCrZr.

Remote maintenance of in-vessel components for ITER

ITER in-vessel components must be remotely maintained due to neutron activation. Components that require maintenance include the blanket shield modules, divertor cassettes and ancillary systems mounted in the vacuum vessel (VV) ports. Maintenance is predominantly accomplished by component removal and transfer to the hot cell facility for repair or waste processing. Component transfer between the VV and the hot cell is performed in sealed casks that dock to the VV ports. An overview of the in-vessel remote maintenance requirements, techniques and equipment is presented.