atw - International Journal for Nuclear Power | 05.2023

atw Vol. 68 (2023) | Ausgabe 5 ı September
ITER and DEMO – Technology Challenges
on the Way to Fusion Power
Klaus Hesch, Robert Stieglitz
Introduction
Nuclear fusion promises virtually unlimited energy production in a sustainable manner with a reduced radiological
risk due to the absence of a nuclear power escalation. However, the technology is complex and still in
the stage of step-wise maturation. While recently, remarkable progress has been achieved at the US Lawrence
Livermore National Laboratory with a laser-driven, inertial fusion approach, the fusion development in Europe
mainly focuses on magnetic confinement fusion, where a solid plasma physics basis beyond the actual
implementation of the fusion reaction itself has been established. The international experimental fusion
reactor ITER, currently under construction at Cadarache in the South of France, as illustrated in Figures 1– 2,
and the design of a Demonstration reactor (DEMO) within the EUROfusion project are the cornerstones of the
European development. Nuclear fusion requires challenging solutions in quite a number of technological and
technology-related areas. Game-changing solutions are being targeted by start-up companies aiming at early
deployment of fusion; still, even if successful, these will not resolve all the challenges/requirements at once,
and will not make obsolete the need for integration of the remaining subsystems and for licensing. This article
provides a brief overview on the technology and related challenges on the way to magnetic fusion energy.
RESEARCH AUS DEN AND UNTERNEHMEN
INNOVATION 37
| Fig. 1
ITER construction at Cadarache, France: Aerial view of construction site.
(Credit :© ITER Organization, http://www.iter.org/)
ITER
ITER shall, for first time, demonstrate a magnetically
confined, self-heating (i.e. “burning”) plasma on
the basis of the D-T fusion reaction:
D + T He + n + 17.6 MeV
According to momentum conservation, 80 % of
the reaction energy (i.e., 14.1 MeV) is carried by
the neutron leaving the plasma chamber domain,
while the remaining 20 % carried by the He ion is
“captured” within the magnetic confinement of the
plasma domain and provides heating of the plasma
fuel through collisions, thus allowing to maintain
the fusion reaction. The goal of ITER is to reach a
Q factor of 10, i.e., to produce 10 times more fusion
power than power injected into the plasma by the
heating systems. This simple consideration, however,
does not take into account the efficiency of
the heating systems, i.e. that the power effectively
injected into the plasma is lower than the power supplied
to the heating systems. E.g., for the Electron
Cyclotron Resonance Heating (ECRH), an efficiency
(or conversion factor) of 50 % appears to be in reach.
Similar arguments for the efficiency hold for a set
of electrically driven technical systems required to
Research and Innovation
ITER and DEMO – Technology Challenges on the Way to Fusion Power Aus ı Klaus den Hesch, Unternehmen
Robert Stieglitz