Abstract
The Conceptual Design Activity (CDA) for the International Fusion Materials Irradiation Facility (IFMIF) has entered its second and final year, and an outline design has been developed. Initial evaluations of the potential of this high flux, high intensity D-Li source have shown that the main materials testing needs can be fulfilled. According to these needs, Vertical Test Assemblies will accommodate test modules for the high flux (0.5 liter, 20 dpa/a, 250-1000 C), the medium flux (6 liter, 1-20 dpa/a, 250-1000 C), the low flux (7.5 liter, 0.1-1 dpa/a), and the very low flux (> 100 liter, 0.01-0.1 dpa/a) regions. Detailed test matrices have been defined for the high and medium flux regions, showing that on the basis of small specimen test technologies, a database for an engineering design of an advanced fusion reactor (DEMO) can be established for a variety of structural materials and ceramic breeders. The design concepts for the Test Cell, including test assemblies, remote handling equipment and Hot Cell Facilities with capacity for investigating all irradiation specimens at the IFMIF site are described.
Highlights
The (IFMIF)Conceptual Design Activity was started in1994under sponsorship of the International Energy Agency (EA)
The mission of this study is to provide a high-flux, high-intensity neutron irradiation testing facility for fusion materials research and development
Earlier efforts investigating this type of facility [1,2], including the Fusion Materials Irradiation Test (FMIT) facility project [3], have concluded that the technically most feasible approach for providing the necessary test conditions utilizes a high-energy deuteron beam, which generates neutrons in a nuclear stripping reaction with a liquid lithium target
Summary
1994under sponsorship of the International Energy Agency (EA). The mission of this study is to provide a high-flux, high-intensity neutron irradiation testing facility for fusion materials research and development. The specific goal of the IFMIF project is (i) to provide a neutron source with an energy spectrum simulating that for a fusion reactor first wallhlanket at sufficient intensity and irradiation volume to test samples of candidate materials up to about full lifetime of anticipated use mainly in a fusion DEMO reactor, and (ii) to calibrate data generated from fission reactors and other simulation experiments with light or heavy ions.
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