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Technology Agreements -
Fusion Power
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Important requirements for a fusion reactor are to ensure sufficient
plasma confinement while protecting plasma-facing components and limiting
plasma impurities. The Implementing Agreement on Toroidal Physics and
Plasma Technologies of Tokamaks with poloidal Field Divertors encompasses
the investigation of toroidal physics and plasma technologies in tokamaks
with poloidal divertors.
Environmental, Safety and Economic Aspects of Fusion Power
The Implementing Agreement on Environmental, Safety and Economic Aspects
of Fusion Power has several areas of interest which include assessment
of environmental impact and safety issues of fusion power, assessment
of the cost of fusion energy and possible role in future energy scenarios.
Fusion Materials
The objective of the Implementing Agreement on Fusion Materials is to
develop and test materials suitable for fusion reactors and components.
This involves research on the effects of fusion reactors operation
conditions on materials and the development of appropriate test facilities,
including the development of a high-flux, high energy neutron source.
The work is aimed at developing data for ITER and other fusion design
activities.
Large Tokamaks
Collaboration between the existing large tokamak facilities, i.e., JET
(EURATOM), JT-60 (Japan) and DIIID and C-MOD (United States), is key
to improve understanding of physics of the operational regime for ITER,
the first, 500-MW fusion experimental reactor, the construction of
which is currently under consideration in the framework of the international
fusion program. The Implementing Agreement promotes collaboration among
the large tokamak facilities and enables teams from each tokamak facility
to co-ordinate their research activities to accelerate scientific and
technological advances.
Nuclear Technology of Fusion Reactors
Breeder blanket and shield technologies, including tritium handling and
processing, and radiation shielding are essential elements of fusion
power technology. The Implementing Agreement on Nuclear Technology
of Fusion Reactors deals with the technology of such components for
tritium production and processing, energy extraction, and radiation
shielding. The Agreement focuses on the first wall, blanket, shield
and plasma-facing components of the fusion reactors.
Plasma Wall Interaction in TEXTOR
Twenty per cent of the thermal power of a fusion reactor has to be transferred
from the hot plasma through the wall components of the burn chamber.
This has to be achieved without overheating and excessive erosion of
the plasma facing materials, without degrading the thermonuclear burn
process by impurities released from the walls, and without burying
too much tritium. Moreover, the helium ashes produced by the fusion
processes have to be removed from the plasma with sufficient efficiency
but without lowering the quality of thermal isolation of the fusion
plasma. The objective of the Implementing Agreement on Plasma Wall
Interaction in TEXTOR is to study these processes, to evaluate their
relative importance and to develop methods for their control.
Reversed Field Pinches
Reversed Field Pinches (RFPs) are one of the possible magnetic confinement
alternatives to the tokamak concept, which is the main fusion magnetic
confinement option. The RFP concept is less developed than the tokamak
but offers potential advantages. The RFP requires a much weaker magnetic
field, which may result in a significant advantage for fusion reactors.
However, the reduced magnetic field also reduces plasma stability and
confinement. Improvement of confinement is one of the major objectives
of on-going research.
Spherical Tori
The goal of the Spherical Tori Implementing Agreement are to co-ordinate fusion energy science R&D activities and strengthen co-operation on Spherical Torus facilities and to advance the scientific and technology basis of magnetic confinement concepts to the Spherical Torus and its further development toward a practical energy source. Work will focus on a new type of compact fusion experimental devices, currently in operation in some IEA countries.
Stellarator Concept
The Stellarator concept is an alternative to the tokamak concept and
has the potential to provide a more effective plasma confinement. It
is, however, less developed than the tokamak concept. Stellarator research
is moving from mid-size experiments to large scale experiments. The underlying
physics has matured and experimental verification of the theoretical
predications have been advanced.
