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22-27 October 2018
Mahatma Mandir Conference Centre
Asia/Kolkata timezone

Nuclear design issues of a stellarator fusion power plant with breeder blanket in comparison to tokamaks

26 Oct 2018, 14:00
4h 45m
Mahatma Mandir Conference Centre

Mahatma Mandir Conference Centre

Gandhinagar (nearest Airport: Ahmedabad), India
Poster FIP - Fusion Engineering, Integration and Power Plant Design P8 Posters


Dr Ulrich Fischer (Karlsruhe Institute of Technology)


The European Roadmap to the realisation of fusion energy considers the stellarator concept as a possible long-term alternative to a tokamak fusion power plant (FPP). A corresponding R&D programme is conducted by the EUROfusion consortium to advance the stellarator concept with the scientific exploitation of the W7-X experiment. The aim is to optimise the stellarator performance, prove the feasibility for steady-state operation, and, on such a basis, study the prospects of a power producing plant based on the helical-axis advanced stellarator (HELIAS) configuration. An important issue towards this goal is the analysis of specific nuclear issues of a HELIAS type FPP equipped with a tritium breeding blanket. This work addresses these issues based on the achievements of the blanket development work conducted within EUROfusion’s Power Plant Physics and Technology (PPPT) programme on a tokamak fusion power demonstration plant (DEMO) and recent results obtained for HELIAS in the neutronics area.
Paper Number FIP/P8-14
Country or International Organization Germany

Primary author

Dr Ulrich Fischer (Karlsruhe Institute of Technology)


Dr Felix Warmer (Max Planck Institute for Plasma Physics) Mr Gaetano Bongiovi (Karlsruhe Institute of Technology) Mr Hauessler Andre (Karlsruhe Institute of Technology) Dr Lorenzo Boccaccini (Karlsruhe Institute of Technology)

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