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EURATOM-FZK Association Forschungszentrum Karlsruhe, IMF-I,
P.O. Box 3640, D-76021 Karlsruhe, Germany
The Oak Ridge National Laboratory, Oak Ridge, TN, USA
1 The University of Tennessee, Knoxville, TN, USA
Los Alamos National Laboratory, Los Alamos, NM 87545, USA
T. Kondo2, H. Katsuta, H. Maekawa
JAERI, Tokai-mura, Ibaraki-ken, 319-11, Japan
2 Tokohu University, Dept. of Machine Intelligence and System Engin.,
Sendai, Japan
ENEA-C.R. Frascati, Via Enrico Fermi 45, 00044 Frascati, Italy
V. Teplyakov
Institute for High Energy Physics, Protvino, Moscow Region, RF
Abstract. There is a global consensus among materials scientists and engineers
that the qualification of materials in an appropriate test environment is
inevitable for design, construction and safe operation of DEMOnstration
fusion reactors as well as for calibration of data generated from fission
reactor and accelerators irradiations. In an evaluation process based on a
series of technical workshops it was concluded that an accelerator driven
D-Li stripping source would be the best choice to fulfill the requirements
within a realistic time frame. In response to this need, an international
design team with members from Europe, Japan, USA and Russia has developed
under the auspices of the IEA during a Conceptual Design Activity Phase
(1994-96) a suitable and feasible concept for an accelerator driven D-Li
stripping source. This IFMIF reference design is based on conservative linac
technology and two parallel operating 125-mA, 40-MeV deuteron beams that are
focused onto a common liquid lithium target with a beam footprint of 50 mm
by 200 mm. The materials testing volume downstream the Li-target is
subdivided into different flux regions: The high flux test region (0.5
liter, 20-55 dpa/full power year), the medium flux test region (6 liter,
1-20 dpa/fpy), and low flux test regions (> 100 liter, < 1 dpa/fpy). The
developed design was the basis fore the present Conceptual Design Evaluation
Phase (1997-98) and for subsequent engineering oriented activities. Based on
comprehensive neutron transport calculations, an evaluation of the
irradiation parameters and the available test volumes has shown that the
users requirements can be fulfilled. Major engineering efforts have been
undertaken to establish an IFMIF design that is based on available and
already proven technologies. The developed design includes extensive
reliability, availability, maintainability as well as safety studies and is
conceived for long-term operation with a total annual facility availability
of at least 70%.
IAEA 2001
