29th Symposium on Fusion Technology (SOFT 2016)

P3.140 Impact on remote maintenance of varying aspect ratio and TF coil quantity for DEMO

7 Sep 2016, 11:00

1h 20m

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

Board: 140

Poster G. Vessel/In-Vessel Engineering and Remote Handling P3 Poster session

Speaker

Dan Wolff (RACE)

Description

As part of the conceptual design studies for a European DEMO, a range of Tokamak geometries are being considered. As identified in the EFDA Roadmap to the realisation of Fusion Energy: “The integration of the Remote Maintenance system within the DEMO plant is an essential task within the DEMO CDA phase. This will involve establishing requirements, functions and interfaces with many other systems to ensure that plant availability and maintainability are considered from the outset.” In order to fulfil this integration requirement these different geometries of DEMO have been assessed for their impact on Remote Maintenance (RM). The aspect ratio and number of TF coils have been identified as the pivotal variables, driving the Tokamak geometry, with significant effects on Remote Maintenance both in terms of technical feasibility and speed of operation. This paper will quantify the effect of varying the number of TF coils and the aspect ratio of a European DEMO on its RM system, in terms of technical feasibility and speed of Remote Maintenance operations. It will compare Tokamak geometries with aspect ratios from 2.6 to 4.0 and 16 or 18 TF coils. The different geometries will be compared using key performance related parameters, with appropriate weightings applied, as defined by RM experts from RACE. The parameters focus on the removal and replacement of the Blanket Multi-Module Segments (MMS) through the upper vertical ports, as this is deemed to be one of the main drivers for the speed and technical feasibility of the RM in DEMO.